============================================================================== | | | | | _____ ___ ____ ____ _ ____ _____ ___ ___ | | | ___|_ _/ ___|| _ \ / \ / ___|_ _| |_ _|_ _| | | | |_ | |\___ \| |_) / _ \| | | |_____| | | | | | | _| | | ___) | __/ ___ \ |___ | |_____| | | | | | |_| |___|____/|_| /_/ \_\____| |_| |___|___| | | | | F I S P A C T - I I | | ------------------- | | | | Transmutation-Activation Inventory Code | | United Kingdom Atomic Energy Authority | | | | Release 4.0 January 2018 | | Copyright (c) 2009-18, UK Atomic Energy Authority | | | ============================================================================== 1 ========================================================================================================= | | | R U N I D E N T I F I C A T I O N I N F O R M A T I O N | | | | INITIAL CROSS SECTION DATA | | Collapsed library timestamp: 17:42:06 17 September 2019 | | EAF source library label: | | FLUX file label: Position #3 Normalization Factor | | | | DECAY DATA | | Condensed library timestamp: 17:43:14 17 September 2019 | | EAF source library label: Decay input from separate files | | | | THIS RUN | | timestamp: 17:44:05 17 September 2019 | | fileroot : y2o35 | | name of FILES file: files | | FISPACT title: * FNS 5 Mins Y2O3 | | | | See the y2o35.log file | | and summary details at the end of this file for further information on files used by this run | | | ========================================================================================================= ------------------------------------------------------------------------------- | NB: IN FOLLOWING TABLES | | ? MEANS CONVERGENCE NOT REACHED FOR NUCLIDE | | & MEANS GAMMA SPECTRUM IS APPROXIMATELY CALCULATED | | # MEANS NUCLIDE IS STABLE | | > MEANS NUCLIDE WAS PRESENT BEFORE IRRADIATION | ------------------------------------------------------------------------------- | | | | V V 1 * * * TIME INTERVAL 1 * * * * * * * TIME IS 0.0000E+00 SECS * * * ELAPSED TIME IS 0.000ps * * * FLUX AMP IS 1.1160E+10 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds O 16 #> 7.98323E+21 2.120E-01 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable O 17 #> 3.04086E+18 8.584E-05 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable O 18 #> 1.60045E+19 4.783E-04 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Y 89 #> 5.33355E+21 7.874E-01 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 4 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 0.00000E+00 0.00000E+00 0.00000E+00 0.00000E+00 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 0.000000E+00 GAMMA BECQUERELS = 0.000000E+00 0 TOTAL ACTIVITY FOR ALL MATERIALS 0.00000E+00 Bq 0.00000E+00 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 0.00000E+00 Bq 0.00000E+00 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 0.00000E+00 kW TOTAL GAMMA HEAT PRODUCTION 0.00000E+00 kW TOTAL HEAT PRODUCTION 0.00000E+00 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 0.00000E+00 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 1.11600E+10 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 0.00000E+00 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 0.00000E+00 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 0.00000E+00 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 0.00000E+00 Sv/kg 0 Total Displacement Rate (n,Ddiss) = 2.33651E+10 Displacements/sec = 1.75205E-12 Displacements Per Atom/sec = 5.52906E-05 DPA/year Total Displacement Rate (n,Dinel) = 5.92436E+10 Displacements/sec = 4.44244E-12 Displacements Per Atom/sec = 1.40193E-04 DPA/year Total Displacement Rate (n,Del ) = 1.17669E+11 Displacements/sec = 8.82352E-12 Displacements Per Atom/sec = 2.78449E-04 DPA/year Total Displacement Rate (n,Dtot ) = 3.14597E+11 Displacements/sec = 2.35904E-11 Displacements Per Atom/sec = 7.44457E-04 DPA/year 0 KERMA RATE (n,Kktot) = 6.88059E+14 eV/sec = 1.10239E-04 kW/kg = 5.52299E-07 kW/cm^3 KERMA RATE (n,Kphot) = 3.68259E+14 eV/sec = 5.90016E-05 kW/kg = 2.95598E-07 kW/cm^3 KERMA RATE (n,Kalph) = 1.53770E+14 eV/sec = 2.46367E-05 kW/kg = 1.23430E-07 kW/cm^3 KERMA RATE (n,Kprot) = 3.22575E+13 eV/sec = 5.16823E-06 kW/kg = 2.58928E-08 kW/cm^3 KERMA RATE (n,Kdiss) = 2.00261E+14 eV/sec = 3.20854E-05 kW/kg = 1.60748E-07 kW/cm^3 KERMA RATE (n,Kfiss) = 0.00000E+00 eV/sec = 0.00000E+00 kW/kg = 0.00000E+00 kW/cm^3 KERMA RATE (n,Kinel) = 5.24011E+14 eV/sec = 8.39558E-05 kW/kg = 4.20618E-07 kW/cm^3 KERMA RATE (n,Knone) = 8.90358E+14 eV/sec = 1.42651E-04 kW/kg = 7.14681E-07 kW/cm^3 KERMA RATE (n,Kel ) = 5.53577E+13 eV/sec = 8.86928E-06 kW/kg = 4.44351E-08 kW/cm^3 KERMA RATE (n,Ktot ) = 9.45715E+14 eV/sec = 1.51520E-04 kW/kg = 7.59117E-07 kW/cm^3 0 GAS RATE (n,Xa ) = 2.56457E+07 atoms per sec = 1.92307E-09 appm/sec GAS RATE (n,Xh ) = 1.90357E-04 atoms per sec = 1.42741E-20 appm/sec GAS RATE (n,Xt ) = 1.48033E+03 atoms per sec = 1.11004E-13 appm/sec GAS RATE (n,Xd ) = 2.05100E+06 atoms per sec = 1.53796E-10 appm/sec GAS RATE (n,Xp ) = 9.38278E+06 atoms per sec = 7.03577E-10 appm/sec COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 1 * * * TIME INTERVAL 2 * * * * * * * TIME IS 3.0000E+02 SECS OR 5.0000E+00 MINS * * * ELAPSED TIME IS 5.000 m * * * FLUX AMP IS 1.1160E+10 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 1 # 2.81483E+09 4.711E-15 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable H 2 # 6.15299E+08 2.058E-15 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 He 4 # 7.69373E+09 5.114E-14 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable C 12 # 3.97030E+09 7.911E-14 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable C 13 # 3.57721E+09 7.724E-14 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 C 15 3.41803E+04 8.520E-19 9.674E+03 4.427E-12 0.00E+00 5.614E-12 1.037E-02 2.128E-09 1.645E-09 2.449E+00 N 15 # 5.87148E+08 1.462E-14 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable N 16 3.07768E+07 8.180E-16 2.992E+06 1.284E-09 1.42E-14 2.215E-09 4.084E+00 2.184E-06 1.646E-06 7.130E+00 N 17 9.68932E+03 2.737E-19 1.611E+03 4.381E-13 2.33E-13 1.148E-14 1.709E-05 1.933E-09 1.385E-09 4.170E+00 O 16 #> 7.98323E+21 2.120E-01 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable O 17 #> 3.04086E+18 8.584E-05 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable O 18 #> 1.60045E+19 4.783E-04 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable F 19 # 3.48119E+03 1.098E-19 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Rb 85 # 7.15625E+04 1.009E-17 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Rb 86 1.25793E+08 1.795E-14 5.414E+01 5.692E-15 0.00E+00 8.135E-16 1.435E-06 1.516E-07 5.035E-08 1.610E+06 Rb 86m 1.22427E+07 1.747E-15 1.391E+05 2.220E-13 0.00E+00 1.217E-11 1.501E-02 4.173E-07 6.817E-08 6.100E+01 Sr 86 # 7.74008E+03 1.104E-18 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Sr 87 # 1.07254E+05 1.548E-17 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Sr 87m 3.11611E+05 4.497E-17 2.131E+01 2.272E-16 0.00E+00 1.095E-15 1.039E-06 6.392E-10 4.474E-10 1.014E+04 Sr 88 # 1.58802E+09 2.318E-13 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Sr 89 3.59938E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58268E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89 #> 5.33355E+21 7.874E-01 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable Y 89m 5.61482E+08 8.289E-14 2.485E+07 2.885E-11 0.00E+00 3.589E-09 5.880E+00 3.976E-03 2.038E-03 1.566E+01 Y 90 2.77859E+07 4.148E-15 8.359E+01 1.246E-14 0.00E+00 3.847E-17 6.808E-13 2.257E-07 1.254E-07 2.304E+05 Y 90m 7.91341E+06 1.181E-15 4.776E+02 3.554E-15 0.00E+00 4.861E-14 5.137E-05 8.120E-08 4.776E-08 1.148E+04 Zr 90 # 1.25315E+04 1.871E-18 0.000E+00 0.000E+00 0.00E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 Stable 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 29 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 7.56540E-04 4.16269E-08 2.22401E-04 9.82158E-04 0 ALPHA BECQUERELS = 1.797202E+01 BETA BECQUERELS = 3.004633E+06 GAMMA BECQUERELS = 2.498733E+07 0 TOTAL ACTIVITY FOR ALL MATERIALS 2.79920E+07 Bq 3.79027E-03 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 2.79920E+07 Bq 3.79027E-03 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 2.46766E-13 kW TOTAL BETA HEAT PRODUCTION 1.31840E-09 kW TOTAL GAMMA HEAT PRODUCTION 5.82228E-09 kW TOTAL HEAT PRODUCTION 7.14093E-09 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 7.14093E-09 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 1.11600E+10 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 3.98040E-03 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 2.04514E-03 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 3.98040E-03 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 2.04514E-03 Sv/kg 0 Total Displacement Rate (n,Ddiss) = 2.33651E+10 Displacements/sec = 1.75205E-12 Displacements Per Atom/sec = 5.52906E-05 DPA/year Total Displacement Rate (n,Dinel) = 5.92436E+10 Displacements/sec = 4.44244E-12 Displacements Per Atom/sec = 1.40193E-04 DPA/year Total Displacement Rate (n,Del ) = 1.17669E+11 Displacements/sec = 8.82352E-12 Displacements Per Atom/sec = 2.78449E-04 DPA/year Total Displacement Rate (n,Dtot ) = 3.14597E+11 Displacements/sec = 2.35904E-11 Displacements Per Atom/sec = 7.44457E-04 DPA/year 0 KERMA RATE (n,Kktot) = 6.88059E+14 eV/sec = 1.10239E-04 kW/kg = 5.52299E-07 kW/cm^3 KERMA RATE (n,Kphot) = 3.68259E+14 eV/sec = 5.90016E-05 kW/kg = 2.95598E-07 kW/cm^3 KERMA RATE (n,Kalph) = 1.53770E+14 eV/sec = 2.46367E-05 kW/kg = 1.23430E-07 kW/cm^3 KERMA RATE (n,Kprot) = 3.22575E+13 eV/sec = 5.16823E-06 kW/kg = 2.58928E-08 kW/cm^3 KERMA RATE (n,Kdiss) = 2.00261E+14 eV/sec = 3.20854E-05 kW/kg = 1.60748E-07 kW/cm^3 KERMA RATE (n,Kfiss) = 0.00000E+00 eV/sec = 0.00000E+00 kW/kg = 0.00000E+00 kW/cm^3 KERMA RATE (n,Kinel) = 5.24011E+14 eV/sec = 8.39558E-05 kW/kg = 4.20618E-07 kW/cm^3 KERMA RATE (n,Knone) = 8.90358E+14 eV/sec = 1.42651E-04 kW/kg = 7.14681E-07 kW/cm^3 KERMA RATE (n,Kel ) = 5.53577E+13 eV/sec = 8.86928E-06 kW/kg = 4.44351E-08 kW/cm^3 KERMA RATE (n,Ktot ) = 9.45715E+14 eV/sec = 1.51520E-04 kW/kg = 7.59117E-07 kW/cm^3 0 GAS RATE (n,Xa ) = 2.56457E+07 atoms per sec = 1.92307E-09 appm/sec GAS RATE (n,Xh ) = 1.90357E-04 atoms per sec = 1.42741E-20 appm/sec GAS RATE (n,Xt ) = 1.48033E+03 atoms per sec = 1.11004E-13 appm/sec GAS RATE (n,Xd ) = 2.05100E+06 atoms per sec = 1.53796E-10 appm/sec GAS RATE (n,Xp ) = 9.38278E+06 atoms per sec = 7.03577E-10 appm/sec 0 GAS RATE (a decay) = 3.59440E+01 atoms per sec = 2.69530E-15 appm/sec 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.3181E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 7.4678E-07 4.4270E-12 9.4697E-07 5.6137E-12 0.0000E+00 0.0000E+00 7 N 6.1793E+08 1.0261E-15 1.5443E-14 2.1675E-04 1.2849E-09 3.7372E-04 2.2154E-09 4.1627E-08 2.4677E-13 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.4812E+03 5.7806E-21 1.0982E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3811E+08 2.2933E-16 1.9702E-14 3.8408E-08 2.2768E-13 2.0531E-06 1.2171E-11 0.0000E+00 0.0000E+00 38 Sr 1.9484E+09 3.2354E-15 2.8500E-13 9.4056E-10 5.5757E-15 1.8492E-10 1.0962E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 4.8688E-06 2.8863E-11 6.0544E-04 3.5891E-09 0.0000E+00 0.0000E+00 40 Zr 1.2531E+04 2.0809E-20 1.8708E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 1.54020E+03 POWER FROM BETA PARTICLES (MeV per Second) 8.22883E+06 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.63398E+07 Total gammas (per cc per second) 1.38043E+08 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 9.26950E+00 Gammas per group (per cc per second) 9.28804E+03 ( 0.010- 0.020 MeV) 1.96119E+03 6.55036E+05 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.38489E+01 1.88073E+03 ( 0.300- 0.400 MeV) 6.80461E+00 9.74031E+01 ( 0.400- 0.600 MeV) 7.61505E+04 7.63028E+05 ( 0.600- 0.800 MeV) 1.05165E+00 7.52684E+00 ( 0.800- 1.000 MeV) 2.23970E+07 1.24677E+08 ( 1.000- 1.220 MeV) 5.07742E+00 2.29170E+01 ( 1.220- 1.440 MeV) 2.63381E-01 9.92134E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 1.18622E+04 3.24753E+04 ( 2.000- 2.500 MeV) 1.47776E+01 3.29048E+01 ( 2.500- 3.000 MeV) 6.90309E+04 1.25762E+05 ( 3.000- 4.000 MeV) 2.68270E-01 3.84009E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 1.26540E+07 1.10255E+07 ( 6.500- 8.000 MeV) 1.07270E+06 7.41273E+05 ( 8.000- 10.000 MeV) 2.12864E+04 1.18494E+04 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 9.99009E+00 Sieverts/hour ( 9.99009E+02 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 2.7992E+07 Total 7.1409E-09 Total 9.9901E+00 Total 3.9804E-03 Total 2.0451E-03 1 Y 89m 2.4848E+07 88.77E+00 Y 89m 3.6174E-09 50.66E+00 Y 89m 5.8797E+00 58.86E+00 Y 89m 3.9756E-03 99.88E+00 Y 89m 2.0375E-03 99.63E+00 2 N 16 2.9920E+06 10.69E+00 N 16 3.4999E-09 49.01E+00 N 16 4.0840E+00 40.88E+00 N 16 2.1841E-06 54.87E-03 Y 88 5.2394E-06 25.62E-02 3 Rb 86m 1.3911E+05 49.70E-02 Rb 86m 1.2392E-11 17.35E-02 Rb 86m 1.5014E-02 15.03E-02 Y 88 1.5480E-06 38.89E-03 N 16 1.6456E-06 80.46E-03 4 C 15 9.6742E+03 34.56E-03 C 15 1.0041E-11 14.06E-02 C 15 1.0374E-02 10.38E-02 Rb 86m 4.1734E-07 10.48E-03 Sr 89 4.5110E-07 22.06E-03 5 N 17 1.6106E+03 57.54E-04 N 17 6.8212E-13 95.52E-04 Y 88 9.7595E-04 97.69E-04 Y 90 2.2570E-07 56.70E-04 Y 90 1.2539E-07 61.31E-04 6 Y 88 1.1908E+03 42.54E-04 Y 88 5.1541E-13 72.18E-04 Y 90m 5.1366E-05 51.42E-05 Rb 86 1.5159E-07 38.08E-04 Rb 86m 6.8166E-08 33.33E-04 7 Y 90m 4.7763E+02 17.06E-04 Y 90m 5.2165E-14 73.05E-05 N 17 1.7094E-05 17.11E-05 Sr 89 1.4846E-07 37.30E-04 Rb 86 5.0350E-08 24.62E-04 8 Y 90 8.3592E+01 29.86E-05 Y 90 1.2502E-14 17.51E-05 Rb 86 1.4346E-06 14.36E-06 Y 90m 8.1198E-08 20.40E-04 Y 90m 4.7763E-08 23.35E-04 9 Sr 89 5.7101E+01 20.40E-05 Rb 86 6.5054E-15 91.10E-06 Sr 87m 1.0392E-06 10.40E-06 C 15 2.1283E-09 53.47E-06 C 15 1.6446E-09 80.42E-06 10 Rb 86 5.4140E+01 19.34E-05 Sr 89 5.3493E-15 74.91E-06 Sr 89 1.3027E-09 13.04E-09 N 17 1.9327E-09 48.56E-06 N 17 1.3851E-09 67.73E-06 11 Sr 87m 2.1306E+01 76.11E-06 Sr 87m 1.3226E-15 18.52E-06 Y 90 6.8076E-13 68.14E-13 Sr 87m 6.3918E-10 16.06E-06 Sr 87m 4.4743E-10 21.88E-06 12 H 3 7.9111E-04 28.26E-10 H 3 7.2341E-22 10.13E-12 0.0000E+00 00.00E+00 H 3 3.3227E-14 83.48E-11 H 3 2.0569E-13 10.06E-09 13 C 14 2.0054E-05 71.64E-12 C 14 1.5896E-22 22.26E-13 0.0000E+00 00.00E+00 C 14 1.1631E-14 29.22E-11 C 14 1.1631E-13 56.87E-10 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.8223E-09 Total 1.3184E-09 1 Y 89m 3.5885E-09 61.63E+00 N 16 1.2844E-09 97.42E+00 2 N 16 2.2154E-09 38.05E+00 Y 89m 2.8846E-11 21.88E-01 3 Rb 86m 1.2170E-11 20.90E-02 C 15 4.4270E-12 33.58E-02 4 C 15 5.6137E-12 96.42E-03 N 17 4.3811E-13 33.23E-03 5 Y 88 5.1420E-13 88.32E-04 Rb 86m 2.2199E-13 16.84E-03 6 Y 90m 4.8612E-14 83.49E-05 Y 90 1.2464E-14 94.54E-05 7 N 17 1.1485E-14 19.73E-05 Rb 86 5.6919E-15 43.17E-05 8 Sr 87m 1.0954E-15 18.81E-06 Sr 89 5.3485E-15 40.57E-05 9 Rb 86 8.1350E-16 13.97E-06 Y 90m 3.5539E-15 26.96E-05 10 Y 90 3.8470E-17 66.07E-08 Y 88 1.2084E-15 91.66E-06 11 Sr 89 7.9509E-19 13.66E-09 Sr 87m 2.2721E-16 17.23E-06 12 0.0000E+00 00.00E+00 H 3 7.2341E-22 54.87E-12 13 0.0000E+00 00.00E+00 C 14 1.5896E-22 12.06E-12 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 2.79920E+07 +/- 3.49E+06 Bq. Error is 1.25E+01 % of the total. Total Heat Production is 7.14093E-09 +/- 5.09E-10 kW. Error is 7.12E+00 % of the total. Total Gamma Dose Rate is 9.99009E+00 +/- 8.27E-01 Sv/hr. Error is 8.27E+00 % of the total. Total Ingestion Dose is 3.98040E-03 +/- 5.59E-04 Sv. Error is 1.40E+01 % of the total. Total Inhalation Dose is 2.04514E-03 +/- 2.86E-04 Sv. Error is 1.40E+01 % of the total. Total Gamma Heat Prod is 5.82228E-09 +/- 5.04E-10 kW. Error is 8.66E+00 % of the total. Total Beta Heat Prod is 1.31840E-09 +/- 4.15E-12 kW. Error is 3.15E-01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 5.61482E+08 7.89E+07 2.485E+07 3.49E+06 3.617E-09 5.09E-10 5.880E+00 8.27E-01 3.976E-03 5.59E-04 2.038E-03 2.86E-04 1.406E+01 N 16 3.07768E+07 0.00E+00 2.992E+06 0.00E+00 3.500E-09 0.00E+00 4.084E+00 0.00E+00 2.184E-06 0.00E+00 1.646E-06 0.00E+00 0.000E+00 Rb 86m 1.22427E+07 3.79E+06 1.391E+05 4.30E+04 1.239E-11 3.83E-12 1.501E-02 4.64E-03 4.173E-07 1.29E-07 6.817E-08 2.11E-08 3.093E+01 C 15 3.41803E+04 6.93E+03 9.674E+03 1.96E+03 1.004E-11 2.04E-12 1.037E-02 2.10E-03 2.128E-09 4.32E-10 1.645E-09 3.34E-10 2.029E+01 Y 88 1.58268E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 N 17 9.68932E+03 4.92E+01 1.611E+03 8.17E+00 6.821E-13 3.46E-15 1.709E-05 8.67E-08 1.933E-09 9.81E-12 1.385E-09 7.03E-12 5.074E-01 Y 90m 7.91341E+06 4.43E+06 4.776E+02 2.67E+02 5.217E-14 2.92E-14 5.137E-05 2.87E-05 8.120E-08 4.54E-08 4.776E-08 2.67E-08 5.596E+01 Rb 86 1.25793E+08 3.19E+07 5.414E+01 1.37E+01 6.505E-15 1.65E-15 1.435E-06 3.63E-07 1.516E-07 3.84E-08 5.035E-08 1.28E-08 2.534E+01 Y 90 2.77859E+07 1.55E+07 8.359E+01 4.67E+01 1.250E-14 6.98E-15 6.808E-13 3.80E-13 2.257E-07 1.26E-07 1.254E-07 7.00E-08 5.581E+01 Sr 89 3.59938E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.11611E+05 2.21E+05 2.131E+01 1.51E+01 1.323E-15 9.39E-16 1.039E-06 7.38E-07 6.392E-10 4.54E-10 4.474E-10 3.18E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 P A T H W A Y A N A L Y S I S F O R I R R A D I A T I O N P H A S E =========================================================================== no of steps = 1 irradiation time = 3.00000E+02 secs flux = 1.11600E+10 n/cm**2/s path floor = 5.00000E-01% of target inventory loop floor = 1.00000E+00% of path inventory max depth = 10 (maximum number of edges between source and target) Pathways are given in order of decreasing dominance of target nuclides as ordered by the dominant nuclide tables above. Target nuclides at the end of the list that do not appear above are those that appear in the dominant lists at later cooling time. Pathways are retained if they contribute more than the path floor percentage of the number of target atoms given by the rate equation solution for the time interval. Loops are retained in a pathway if they contribute more than the loop floor percentage of the number of target atoms created along the pathway. Pathways are analysed between the following source and target nuclides: Source Nuclides O 16 O 17 O 18 Y 89 Target Nuclides Y 89m N 16 Rb 86m C 15 Y 88 N 17 Y 90m Rb 86 Y 90 Sr 89 Sr 87m H 3 C 14 Listed below are all significant paths and loops ordered by target nuclide. The first line for each target nuclide gives the nuclide name and the percentage of the total number of atoms given by the number of significant paths shown. The first line for each pathway indentifies a path or loop, gives its number and its respective percentage contribution to the target nuclide inventory. The remainder of the line gives the nuclides on the path (or loop) from source to target, and the type of graph edge joining them. Edge types (r,R), (d,D) and (b,B) respectively denote reaction, decay and combined reaction and decay edges from short and long lived parent. L and S denote short and long lived target nuclides. Short-lived nuclides have half lives less than the time interval and long-lived have half live greater. Shown below each edge is a list showing the percentage that each reaction and decay make towards the total rate for the edge for primary products. If the edge daughter is a secondary then isomeric state of the primary product of the reaction decay is also displayed. Significant loops are displayed directly after their path, and their percentages are their part of the total path percentage. Target nuclide Y 89m 100.000% of inventory given by 1 path -------------------- path 1 100.000% Y 89 ---(R)--- Y 89m---(S)--- 100.00%(n,n) Target nuclide N 16 99.960% of inventory given by 1 path -------------------- path 1 99.960% O 16 ---(R)--- N 16 ---(S)--- 100.00%(n,p) Target nuclide Rb 86m 100.000% of inventory given by 1 path -------------------- path 1 100.000% Y 89 ---(R)--- Rb 86m---(S)--- 100.00%(n,a) Target nuclide C 15 100.000% of inventory given by 1 path -------------------- path 1 100.000% O 18 ---(R)--- C 15 ---(S)--- 100.00%(n,a) Target nuclide Y 88 100.000% of inventory given by 1 path -------------------- path 1 100.000% Y 89 ---(R)--- Y 88 ---(L)--- 100.00%(n,2n) Target nuclide N 17 100.000% of inventory given by 2 paths -------------------- path 1 99.002% O 17 ---(R)--- N 17 ---(S)--- 100.00%(n,p) path 2 0.998% O 18 ---(R)--- N 17 ---(S)--- 100.00%(n,d) Target nuclide Y 90m 100.000% of inventory given by 1 path -------------------- path 1 100.000% Y 89 ---(R)--- Y 90m---(L)--- 100.00%(n,g) Target nuclide Rb 86 100.000% of inventory given by 2 paths -------------------- path 1 75.422% Y 89 ---(R)--- Rb 86 ---(L)--- 100.00%(n,a) path 2 24.578% Y 89 ---(R)--- Rb 86m---(b)--- Rb 86 ---(L)--- 100.00%(n,a) 100.00%(IT) 0.00%(n,E) 0.00%(n,n) Target nuclide Y 90 99.741% of inventory given by 1 path -------------------- path 1 99.741% Y 89 ---(R)--- Y 90 ---(L)--- 100.00%(n,g) Target nuclide Sr 89 100.000% of inventory given by 1 path -------------------- path 1 100.000% Y 89 ---(R)--- Sr 89 ---(L)--- 100.00%(n,p) Target nuclide Sr 87m 100.000% of inventory given by 1 path -------------------- path 1 100.000% Y 89 ---(R)--- Sr 87m---(L)--- 100.00%(n,t) Target nuclide H 3 99.993% of inventory given by 2 paths -------------------- path 1 5.673% O 18 ---(R)--- H 3 ---(L)--- 100.00%(n,t) path 2 94.320% Y 89 ---(R)--- H 3 ---(L)--- 24.84%(n,t) 75.16%(n,t)m Target nuclide C 14 100.000% of inventory given by 2 paths -------------------- path 1 44.690% O 17 ---(R)--- C 14 ---(L)--- 100.00%(n,a) path 2 55.310% O 18 ---(R)--- C 14 ---(L)--- 100.00%(n,na) G E N E R I C P A T H W A Y S F O R I R R A D I A T I O N P H A S E ========================================================================== All pathways differing only by an isomeric decay (IT) edge are regarded as the same generic pathway and are shown here. Individual pathways are shown above. Each generic pathway (gpath) has a path number, the percentage of the target nuclide atoms generated along the pathway and the source to target edges. Target nuclide Rb 86 100.000% of inventory given by 2 paths -------------------- path 1 100.000% Y 89 ---(R)--- Rb 86 ---(L)--- This generic pathway is the sum of 2 pathways 1 * * * TIME INTERVAL 3 * * * COOLING TIME IS 6.6000E+01 SECS OR 1.1000E+00 MINS * * * ELAPSED TIME IS 1.100 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 N 16 ? 5.05934E+04 1.345E-18 4.918E+03 2.111E-12 2.34E-17 3.642E-12 6.714E-03 3.590E-09 2.705E-09 7.130E+00 Rb 86 1.32248E+08 1.887E-14 5.692E+01 5.984E-15 0.00E+00 8.552E-16 1.508E-06 1.594E-07 5.293E-08 1.610E+06 Rb 86m 5.78326E+06 8.250E-16 6.572E+04 1.049E-13 0.00E+00 5.749E-12 7.092E-03 1.971E-07 3.220E-08 6.100E+01 Sr 87m 3.10208E+05 4.477E-17 2.121E+01 2.262E-16 0.00E+00 1.090E-15 1.035E-06 6.363E-10 4.454E-10 1.014E+04 Sr 89 3.59934E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58268E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m ? 3.02609E+07 4.467E-15 1.339E+06 1.555E-12 0.00E+00 1.934E-10 3.169E-01 2.143E-04 1.098E-04 1.566E+01 Y 90 2.78118E+07 4.152E-15 8.367E+01 1.248E-14 0.00E+00 3.851E-17 6.814E-13 2.259E-07 1.255E-07 2.304E+05 Y 90m 7.88195E+06 1.177E-15 4.757E+02 3.540E-15 0.00E+00 4.842E-14 5.116E-05 8.088E-08 4.757E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 11 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 3.81535E-05 3.94789E-12 6.40977E-07 3.43043E-05 0 ALPHA BECQUERELS = 2.951080E-02 BETA BECQUERELS = 6.306973E+03 GAMMA BECQUERELS = 1.405372E+06 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.41168E+06 Bq 1.91149E-04 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.41168E+06 Bq 1.91149E-04 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 2.34033E-17 kW TOTAL BETA HEAT PRODUCTION 3.79974E-12 kW TOTAL GAMMA HEAT PRODUCTION 2.03358E-10 kW TOTAL HEAT PRODUCTION 2.07157E-10 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 2.07157E-10 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16629E-04 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 1.15763E-04 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16629E-04 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 1.15763E-04 Sv/kg 0 GAS RATE (a decay) = 5.90216E-02 atoms per sec = 4.42579E-18 appm/sec 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.7096E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8723E+08 9.7512E-16 1.4627E-14 3.5618E-07 2.1115E-12 6.1434E-07 3.6419E-12 3.9479E-12 2.3403E-17 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9039E+03 6.4826E-21 1.2316E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3810E+08 2.2933E-16 1.9702E-14 1.8699E-08 1.1085E-13 9.6993E-07 5.7498E-12 0.0000E+00 0.0000E+00 38 Sr 1.9485E+09 3.2355E-15 2.8502E-13 9.4038E-10 5.5746E-15 1.8408E-10 1.0913E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.6515E-07 1.5718E-12 3.2720E-05 1.9396E-10 0.0000E+00 0.0000E+00 40 Zr 1.8052E+04 2.9976E-20 2.6950E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 1.46072E-01 POWER FROM BETA PARTICLES (MeV per Second) 2.37161E+04 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 1.26926E+06 Total gammas (per cc per second) 7.15579E+06 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 6.07555E-01 Gammas per group (per cc per second) 6.08770E+02 ( 0.010- 0.020 MeV) 1.24051E+02 4.14330E+04 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.34758E+01 1.87325E+03 ( 0.300- 0.400 MeV) 6.77397E+00 9.69645E+01 ( 0.400- 0.600 MeV) 3.60825E+04 3.61547E+05 ( 0.600- 0.800 MeV) 1.04747E+00 7.49692E+00 ( 0.800- 1.000 MeV) 1.20802E+06 6.72466E+06 ( 1.000- 1.220 MeV) 5.33800E+00 2.40931E+01 ( 1.220- 1.440 MeV) 2.63380E-01 9.92129E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.18738E+03 5.98840E+03 ( 2.000- 2.500 MeV) 2.06707E-06 4.60267E-06 ( 2.500- 3.000 MeV) 1.33436E+02 2.43095E+02 ( 3.000- 4.000 MeV) 2.68268E-01 3.84007E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 2.07444E+04 1.80747E+04 ( 6.500- 8.000 MeV) 1.76339E+03 1.21856E+03 ( 8.000- 10.000 MeV) 3.48983E+01 1.94267E+01 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 3.31719E-01 Sieverts/hour ( 3.31719E+01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.4117E+06 Total 2.0716E-10 Total 3.3172E-01 Total 2.1663E-04 Total 1.1576E-04 1 Y 89m 1.3392E+06 94.86E+00 Y 89m 1.9496E-10 94.11E+00 Y 89m 3.1688E-01 95.53E+00 Y 89m 2.1427E-04 98.91E+00 Y 89m 1.0981E-04 94.86E+00 2 Rb 86m 6.5716E+04 46.55E-01 Rb 86m 5.8538E-12 28.26E-01 Rb 86m 7.0923E-03 21.38E-01 Y 88 1.5480E-06 71.46E-02 Y 88 5.2394E-06 45.26E-01 3 N 16 4.9185E+03 34.84E-02 N 16 5.7534E-12 27.77E-01 N 16 6.7136E-03 20.24E-01 Y 90 2.2591E-07 10.43E-02 Sr 89 4.5110E-07 38.97E-02 4 Y 88 1.1908E+03 84.35E-03 Y 88 5.1541E-13 24.88E-02 Y 88 9.7594E-04 29.42E-02 Rb 86m 1.9715E-07 91.01E-03 Y 90 1.2551E-07 10.84E-02 5 Y 90m 4.7574E+02 33.70E-03 Y 90m 5.1958E-14 25.08E-03 Y 90m 5.1161E-05 15.42E-03 Rb 86 1.5937E-07 73.57E-03 Rb 86 5.2934E-08 45.73E-03 6 Y 90 8.3671E+01 59.27E-04 Y 90 1.2514E-14 60.41E-04 Rb 86 1.5082E-06 45.47E-05 Sr 89 1.4846E-07 68.53E-03 Y 90m 4.7574E-08 41.10E-03 7 Sr 89 5.7101E+01 40.45E-04 Rb 86 6.8392E-15 33.01E-04 Sr 87m 1.0345E-06 31.19E-05 Y 90m 8.0875E-08 37.33E-03 Rb 86m 3.2201E-08 27.82E-03 8 Rb 86 5.6919E+01 40.32E-04 Sr 89 5.3492E-15 25.82E-04 Sr 89 1.3027E-09 39.27E-08 N 16 3.5905E-09 16.57E-04 N 16 2.7052E-09 23.37E-04 9 Sr 87m 2.1210E+01 15.02E-04 Sr 87m 1.3167E-15 63.56E-05 Y 90 6.8140E-13 20.54E-11 Sr 87m 6.3630E-10 29.37E-05 Sr 87m 4.4541E-10 38.48E-05 10 H 3 7.9111E-04 56.04E-09 H 3 7.2341E-22 34.92E-11 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.34E-09 H 3 2.0569E-13 17.77E-08 11 C 14 2.0054E-05 14.21E-10 C 14 1.5896E-22 76.73E-12 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.69E-10 C 14 1.1631E-13 10.05E-08 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 2.0336E-10 Total 3.7997E-12 1 Y 89m 1.9340E-10 95.10E+00 N 16 2.1115E-12 55.57E+00 2 Rb 86m 5.7490E-12 28.27E-01 Y 89m 1.5546E-12 40.91E+00 3 N 16 3.6419E-12 17.91E-01 Rb 86m 1.0486E-13 27.60E-01 4 Y 88 5.1420E-13 25.29E-02 Y 90 1.2475E-14 32.83E-02 5 Y 90m 4.8418E-14 23.81E-03 Rb 86 5.9840E-15 15.75E-02 6 Sr 87m 1.0905E-15 53.62E-05 Sr 89 5.3484E-15 14.08E-02 7 Rb 86 8.5525E-16 42.06E-05 Y 90m 3.5397E-15 93.16E-03 8 Y 90 3.8506E-17 18.94E-06 Y 88 1.2084E-15 31.80E-03 9 Sr 89 7.9508E-19 39.10E-08 Sr 87m 2.2619E-16 59.53E-04 10 0.0000E+00 00.00E+00 H 3 7.2341E-22 19.04E-09 11 0.0000E+00 00.00E+00 C 14 1.5896E-22 41.83E-10 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.41168E+06 +/- 1.89E+05 Bq. Error is 1.34E+01 % of the total. Total Heat Production is 2.07157E-10 +/- 2.75E-11 kW. Error is 1.33E+01 % of the total. Total Gamma Dose Rate is 3.31719E-01 +/- 4.46E-02 Sv/hr. Error is 1.34E+01 % of the total. Total Ingestion Dose is 2.16629E-04 +/- 3.01E-05 Sv. Error is 1.39E+01 % of the total. Total Inhalation Dose is 1.15763E-04 +/- 1.54E-05 Sv. Error is 1.33E+01 % of the total. Total Gamma Heat Prod is 2.03358E-10 +/- 2.72E-11 kW. Error is 1.34E+01 % of the total. Total Beta Heat Prod is 3.79974E-12 +/- 2.21E-13 kW. Error is 5.82E+00 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 3.02609E+07 4.25E+06 1.339E+06 1.88E+05 1.950E-10 2.74E-11 3.169E-01 4.45E-02 2.143E-04 3.01E-05 1.098E-04 1.54E-05 1.406E+01 N 16 5.05934E+04 0.00E+00 4.918E+03 0.00E+00 5.753E-12 0.00E+00 6.714E-03 0.00E+00 3.590E-09 0.00E+00 2.705E-09 0.00E+00 0.000E+00 Rb 86m 5.78326E+06 1.79E+06 6.572E+04 2.03E+04 5.854E-12 1.81E-12 7.092E-03 2.19E-03 1.971E-07 6.10E-08 3.220E-08 9.96E-09 3.093E+01 Y 88 1.58268E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.88195E+06 4.41E+06 4.757E+02 2.66E+02 5.196E-14 2.91E-14 5.116E-05 2.86E-05 8.088E-08 4.53E-08 4.757E-08 2.66E-08 5.596E+01 Rb 86 1.32248E+08 3.35E+07 5.692E+01 1.44E+01 6.839E-15 1.73E-15 1.508E-06 3.82E-07 1.594E-07 4.04E-08 5.293E-08 1.34E-08 2.534E+01 Y 90 2.78118E+07 1.55E+07 8.367E+01 4.67E+01 1.251E-14 6.98E-15 6.814E-13 3.80E-13 2.259E-07 1.26E-07 1.255E-07 7.00E-08 5.581E+01 Sr 89 3.59934E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.10208E+05 2.20E+05 2.121E+01 1.51E+01 1.317E-15 9.35E-16 1.035E-06 7.35E-07 6.363E-10 4.52E-10 4.454E-10 3.16E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 4 * * * COOLING TIME IS 1.6000E+01 SECS * * * ELAPSED TIME IS 1.367 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 N 16 1.07169E+04 2.848E-19 1.042E+03 4.473E-13 4.96E-18 7.714E-13 1.422E-03 7.606E-10 5.730E-10 7.130E+00 Rb 86 1.33209E+08 1.900E-14 5.733E+01 6.027E-15 0.00E+00 8.615E-16 1.519E-06 1.605E-07 5.332E-08 1.610E+06 Rb 86m 4.82185E+06 6.879E-16 5.479E+04 8.743E-14 0.00E+00 4.793E-12 5.913E-03 1.644E-07 2.685E-08 6.100E+01 Sr 87m 3.09869E+05 4.472E-17 2.119E+01 2.259E-16 0.00E+00 1.089E-15 1.033E-06 6.356E-10 4.449E-10 1.014E+04 Sr 89 3.59933E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58267E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m 1.49067E+07 2.201E-15 6.597E+05 7.658E-13 0.00E+00 9.527E-11 1.561E-01 1.055E-04 5.409E-05 1.566E+01 Y 90 2.78181E+07 4.153E-15 8.369E+01 1.248E-14 0.00E+00 3.852E-17 6.816E-13 2.260E-07 1.255E-07 2.304E+05 Y 90m 7.87434E+06 1.176E-15 4.753E+02 3.536E-15 0.00E+00 4.837E-14 5.111E-05 8.080E-08 4.753E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 11 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 1.93891E-05 8.36260E-13 2.24245E-07 1.71052E-05 0 ALPHA BECQUERELS = 6.251105E-03 BETA BECQUERELS = 2.430811E+03 GAMMA BECQUERELS = 7.149656E+05 0 TOTAL ACTIVITY FOR ALL MATERIALS 7.17396E+05 Bq 9.71393E-05 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 7.17396E+05 Bq 9.71393E-05 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 4.95739E-18 kW TOTAL BETA HEAT PRODUCTION 1.32933E-12 kW TOTAL GAMMA HEAT PRODUCTION 1.01400E-10 kW TOTAL HEAT PRODUCTION 1.02730E-10 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 1.02730E-10 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 1.07878E-04 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 6.00383E-05 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 1.07878E-04 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 6.00383E-05 Sv/kg 0 GAS RATE (a decay) = 1.25022E-02 atoms per sec = 9.37491E-19 appm/sec 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.8045E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8719E+08 9.7506E-16 1.4626E-14 7.5448E-08 4.4726E-13 1.3013E-07 7.7143E-13 8.3626E-13 4.9574E-18 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9358E+03 6.5356E-21 1.2417E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3810E+08 2.2932E-16 1.9701E-14 1.5766E-08 9.3460E-14 8.0872E-07 4.7941E-12 0.0000E+00 0.0000E+00 38 Sr 1.9485E+09 3.2355E-15 2.8502E-13 9.4033E-10 5.5743E-15 1.8388E-10 1.0901E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 1.3209E-07 7.8304E-13 1.6166E-05 9.5834E-11 0.0000E+00 0.0000E+00 40 Zr 1.9391E+04 3.2199E-20 2.8949E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 3.09416E-02 POWER FROM BETA PARTICLES (MeV per Second) 8.29706E+03 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 6.32892E+05 Total gammas (per cc per second) 3.65300E+06 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 3.46929E-01 Gammas per group (per cc per second) 3.47623E+02 ( 0.010- 0.020 MeV) 6.97224E+01 2.32873E+04 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.33856E+01 1.87145E+03 ( 0.300- 0.400 MeV) 6.76656E+00 9.68585E+01 ( 0.400- 0.600 MeV) 3.01188E+04 3.01791E+05 ( 0.600- 0.800 MeV) 1.04646E+00 7.48968E+00 ( 0.800- 1.000 MeV) 5.95589E+05 3.31544E+06 ( 1.000- 1.220 MeV) 5.37677E+00 2.42681E+01 ( 1.220- 1.440 MeV) 2.63379E-01 9.92128E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17482E+03 5.95402E+03 ( 2.000- 2.500 MeV) 2.06753E-06 4.60371E-06 ( 2.500- 3.000 MeV) 4.40203E+01 8.01969E+01 ( 3.000- 4.000 MeV) 2.68268E-01 3.84006E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 4.39417E+03 3.82866E+03 ( 6.500- 8.000 MeV) 3.73528E+02 2.58121E+02 ( 8.000- 10.000 MeV) 7.39230E+00 4.11505E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.64464E-01 Sieverts/hour ( 1.64464E+01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 7.1740E+05 Total 1.0273E-10 Total 1.6446E-01 Total 1.0788E-04 Total 6.0038E-05 1 Y 89m 6.5968E+05 91.95E+00 Y 89m 9.6037E-11 93.49E+00 Y 89m 1.5610E-01 94.91E+00 Y 89m 1.0555E-04 97.84E+00 Y 89m 5.4094E-05 90.10E+00 2 Rb 86m 5.4791E+04 76.37E-01 Rb 86m 4.8807E-12 47.51E-01 Rb 86m 5.9133E-03 35.95E-01 Y 88 1.5480E-06 14.35E-01 Y 88 5.2394E-06 87.27E-01 3 Y 88 1.1908E+03 16.60E-02 N 16 1.2187E-12 11.86E-01 N 16 1.4221E-03 86.47E-02 Y 90 2.2596E-07 20.95E-02 Sr 89 4.5109E-07 75.13E-02 4 N 16 1.0419E+03 14.52E-02 Y 88 5.1541E-13 50.17E-02 Y 88 9.7594E-04 59.34E-02 Rb 86m 1.6437E-07 15.24E-02 Y 90 1.2553E-07 20.91E-02 5 Y 90m 4.7528E+02 66.25E-03 Y 90m 5.1908E-14 50.53E-03 Y 90m 5.1112E-05 31.08E-03 Rb 86 1.6053E-07 14.88E-02 Rb 86 5.3319E-08 88.81E-03 6 Y 90 8.3689E+01 11.67E-03 Y 90 1.2517E-14 12.18E-03 Rb 86 1.5191E-06 92.37E-05 Sr 89 1.4846E-07 13.76E-02 Y 90m 4.7528E-08 79.16E-03 7 Rb 86 5.7332E+01 79.92E-04 Rb 86 6.8889E-15 67.06E-04 Sr 87m 1.0334E-06 62.84E-05 Y 90m 8.0797E-08 74.90E-03 Rb 86m 2.6848E-08 44.72E-03 8 Sr 89 5.7101E+01 79.59E-04 Sr 89 5.3492E-15 52.07E-04 Sr 89 1.3027E-09 79.21E-08 N 16 7.6055E-10 70.50E-05 N 16 5.7302E-10 95.44E-05 9 Sr 87m 2.1187E+01 29.53E-04 Sr 87m 1.3152E-15 12.80E-04 Y 90 6.8155E-13 41.44E-11 Sr 87m 6.3561E-10 58.92E-05 Sr 87m 4.4493E-10 74.11E-05 10 H 3 7.9111E-04 11.03E-08 H 3 7.2341E-22 70.42E-11 0.0000E+00 00.00E+00 H 3 3.3227E-14 30.80E-09 H 3 2.0569E-13 34.26E-08 11 C 14 2.0054E-05 27.95E-10 C 14 1.5896E-22 15.47E-11 0.0000E+00 00.00E+00 C 14 1.1631E-14 10.78E-09 C 14 1.1631E-13 19.37E-08 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 1.0140E-10 Total 1.3293E-12 1 Y 89m 9.5271E-11 93.96E+00 Y 89m 7.6582E-13 57.61E+00 2 Rb 86m 4.7932E-12 47.27E-01 N 16 4.4726E-13 33.65E+00 3 N 16 7.7143E-13 76.08E-02 Rb 86m 8.7432E-14 65.77E-01 4 Y 88 5.1420E-13 50.71E-02 Y 90 1.2478E-14 93.87E-02 5 Y 90m 4.8372E-14 47.70E-03 Rb 86 6.0275E-15 45.34E-02 6 Sr 87m 1.0893E-15 10.74E-04 Sr 89 5.3484E-15 40.23E-02 7 Rb 86 8.6146E-16 84.96E-05 Y 90m 3.5363E-15 26.60E-02 8 Y 90 3.8515E-17 37.98E-06 Y 88 1.2084E-15 90.90E-03 9 Sr 89 7.9508E-19 78.41E-08 Sr 87m 2.2594E-16 17.00E-03 10 0.0000E+00 00.00E+00 H 3 7.2341E-22 54.42E-09 11 0.0000E+00 00.00E+00 C 14 1.5896E-22 11.96E-09 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 7.17396E+05 +/- 9.43E+04 Bq. Error is 1.31E+01 % of the total. Total Heat Production is 1.02730E-10 +/- 1.36E-11 kW. Error is 1.32E+01 % of the total. Total Gamma Dose Rate is 1.64464E-01 +/- 2.20E-02 Sv/hr. Error is 1.34E+01 % of the total. Total Ingestion Dose is 1.07878E-04 +/- 1.48E-05 Sv. Error is 1.38E+01 % of the total. Total Inhalation Dose is 6.00383E-05 +/- 7.62E-06 Sv. Error is 1.27E+01 % of the total. Total Gamma Heat Prod is 1.01400E-10 +/- 1.35E-11 kW. Error is 1.33E+01 % of the total. Total Beta Heat Prod is 1.32933E-12 +/- 1.11E-13 kW. Error is 8.37E+00 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 1.49067E+07 2.10E+06 6.597E+05 9.27E+04 9.604E-11 1.35E-11 1.561E-01 2.19E-02 1.055E-04 1.48E-05 5.409E-05 7.60E-06 1.406E+01 N 16 1.07169E+04 0.00E+00 1.042E+03 0.00E+00 1.219E-12 0.00E+00 1.422E-03 0.00E+00 7.606E-10 0.00E+00 5.730E-10 0.00E+00 0.000E+00 Rb 86m 4.82185E+06 1.49E+06 5.479E+04 1.69E+04 4.881E-12 1.51E-12 5.913E-03 1.83E-03 1.644E-07 5.08E-08 2.685E-08 8.30E-09 3.093E+01 Y 88 1.58267E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.87434E+06 4.41E+06 4.753E+02 2.66E+02 5.191E-14 2.90E-14 5.111E-05 2.86E-05 8.080E-08 4.52E-08 4.753E-08 2.66E-08 5.596E+01 Rb 86 1.33209E+08 3.38E+07 5.733E+01 1.45E+01 6.889E-15 1.75E-15 1.519E-06 3.85E-07 1.605E-07 4.07E-08 5.332E-08 1.35E-08 2.534E+01 Y 90 2.78181E+07 1.55E+07 8.369E+01 4.67E+01 1.252E-14 6.99E-15 6.816E-13 3.80E-13 2.260E-07 1.26E-07 1.255E-07 7.01E-08 5.581E+01 Sr 89 3.59933E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.09869E+05 2.20E+05 2.119E+01 1.50E+01 1.315E-15 9.34E-16 1.033E-06 7.34E-07 6.356E-10 4.51E-10 4.449E-10 3.16E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 5 * * * COOLING TIME IS 1.6000E+01 SECS * * * ELAPSED TIME IS 1.633 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 N 16 2.26258E+03 6.014E-20 2.200E+02 9.443E-14 1.05E-18 1.629E-13 3.002E-04 1.606E-10 1.210E-10 7.130E+00 Rb 86 1.34010E+08 1.912E-14 5.768E+01 6.064E-15 0.00E+00 8.666E-16 1.528E-06 1.615E-07 5.364E-08 1.610E+06 Rb 86m 4.02027E+06 5.735E-16 4.568E+04 7.290E-14 0.00E+00 3.996E-12 4.930E-03 1.370E-07 2.238E-08 6.100E+01 Sr 87m 3.09530E+05 4.467E-17 2.116E+01 2.257E-16 0.00E+00 1.088E-15 1.032E-06 6.349E-10 4.444E-10 1.014E+04 Sr 89 3.59932E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58267E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m 7.34302E+06 1.084E-15 3.250E+05 3.772E-13 0.00E+00 4.693E-11 7.689E-02 5.199E-05 2.665E-05 1.566E+01 Y 90 2.78244E+07 4.154E-15 8.371E+01 1.248E-14 0.00E+00 3.852E-17 6.817E-13 2.260E-07 1.256E-07 2.304E+05 Y 90m 7.86674E+06 1.174E-15 4.748E+02 3.533E-15 0.00E+00 4.832E-14 5.106E-05 8.072E-08 4.748E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 11 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 1.00742E-05 1.76553E-13 9.67307E-08 8.71353E-06 0 ALPHA BECQUERELS = 1.319748E-03 BETA BECQUERELS = 1.609285E+03 GAMMA BECQUERELS = 3.711350E+05 0 TOTAL ACTIVITY FOR ALL MATERIALS 3.72744E+05 Bq 5.04716E-05 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 3.72744E+05 Bq 5.04716E-05 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 1.04662E-18 kW TOTAL BETA HEAT PRODUCTION 5.73424E-13 kW TOTAL GAMMA HEAT PRODUCTION 5.16542E-11 kW TOTAL HEAT PRODUCTION 5.22277E-11 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.22277E-11 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 5.42956E-05 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 3.25865E-05 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 5.42956E-05 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 3.25865E-05 Sv/kg 0 GAS RATE (a decay) = 2.63950E-03 atoms per sec = 1.97925E-19 appm/sec 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.8994E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 1.5929E-08 9.4427E-14 2.7474E-08 1.6287E-13 1.7655E-13 1.0466E-18 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9570E+03 6.5707E-21 1.2483E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3810E+08 2.2932E-16 1.9701E-14 1.3320E-08 7.8961E-14 6.7430E-07 3.9973E-12 0.0000E+00 0.0000E+00 38 Sr 1.9485E+09 3.2356E-15 2.8502E-13 9.4029E-10 5.5741E-15 1.8368E-10 1.0889E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 6.6542E-08 3.9446E-13 8.0116E-06 4.7493E-11 0.0000E+00 0.0000E+00 40 Zr 2.0730E+04 3.4423E-20 3.0948E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 6.53246E-03 POWER FROM BETA PARTICLES (MeV per Second) 3.57903E+03 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.22400E+05 Total gammas (per cc per second) 1.91123E+06 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 2.14195E-01 Gammas per group (per cc per second) 2.14623E+02 ( 0.010- 0.020 MeV) 4.24392E+01 1.41747E+04 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.32954E+01 1.86964E+03 ( 0.300- 0.400 MeV) 6.75917E+00 9.67526E+01 ( 0.400- 0.600 MeV) 2.51465E+04 2.51968E+05 ( 0.600- 0.800 MeV) 1.04545E+00 7.48245E+00 ( 0.800- 1.000 MeV) 2.93896E+05 1.63602E+06 ( 1.000- 1.220 MeV) 5.40909E+00 2.44140E+01 ( 1.220- 1.440 MeV) 2.63379E-01 9.92127E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17216E+03 5.94672E+03 ( 2.000- 2.500 MeV) 2.06800E-06 4.60474E-06 ( 2.500- 3.000 MeV) 2.50630E+01 4.56603E+01 ( 3.000- 4.000 MeV) 2.68268E-01 3.84006E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 9.27707E+02 8.08315E+02 ( 6.500- 8.000 MeV) 7.88601E+01 5.44951E+01 ( 8.000- 10.000 MeV) 1.56068E+00 8.68778E-01 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 8.31542E-02 Sieverts/hour ( 8.31542E+00 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 3.7274E+05 Total 5.2228E-11 Total 8.3154E-02 Total 5.4296E-05 Total 3.2587E-05 1 Y 89m 3.2496E+05 87.18E+00 Y 89m 4.7308E-11 90.58E+00 Y 89m 7.6894E-02 92.47E+00 Y 89m 5.1993E-05 95.76E+00 Y 89m 2.6646E-05 81.77E+00 2 Rb 86m 4.5683E+04 12.26E+00 Rb 86m 4.0693E-12 77.92E-01 Rb 86m 4.9302E-03 59.29E-01 Y 88 1.5480E-06 28.51E-01 Y 88 5.2394E-06 16.08E+00 3 Y 88 1.1908E+03 31.95E-02 Y 88 5.1541E-13 98.68E-02 Y 88 9.7594E-04 11.74E-01 Y 90 2.2601E-07 41.63E-02 Sr 89 4.5109E-07 13.84E-01 4 Y 90m 4.7482E+02 12.74E-02 N 16 2.5729E-13 49.26E-02 N 16 3.0024E-04 36.11E-02 Rb 86 1.6149E-07 29.74E-02 Y 90 1.2556E-07 38.53E-02 5 N 16 2.1996E+02 59.01E-03 Y 90m 5.1858E-14 99.29E-03 Y 90m 5.1063E-05 61.41E-03 Sr 89 1.4846E-07 27.34E-02 Rb 86 5.3639E-08 16.46E-02 6 Y 90 8.3708E+01 22.46E-03 Y 90 1.2520E-14 23.97E-03 Rb 86 1.5283E-06 18.38E-04 Rb 86m 1.3705E-07 25.24E-02 Y 90m 4.7482E-08 14.57E-02 7 Rb 86 5.7677E+01 15.47E-03 Rb 86 6.9303E-15 13.27E-03 Sr 87m 1.0323E-06 12.41E-04 Y 90m 8.0719E-08 14.87E-02 Rb 86m 2.2384E-08 68.69E-03 8 Sr 89 5.7100E+01 15.32E-03 Sr 89 5.3492E-15 10.24E-03 Sr 89 1.3027E-09 15.67E-07 Sr 87m 6.3491E-10 11.69E-04 Sr 87m 4.4444E-10 13.64E-04 9 Sr 87m 2.1164E+01 56.78E-04 Sr 87m 1.3138E-15 25.15E-04 Y 90 6.8171E-13 81.98E-11 N 16 1.6057E-10 29.57E-05 N 16 1.2098E-10 37.12E-05 10 H 3 7.9111E-04 21.22E-08 H 3 7.2341E-22 13.85E-10 0.0000E+00 00.00E+00 H 3 3.3227E-14 61.20E-09 H 3 2.0569E-13 63.12E-08 11 C 14 2.0054E-05 53.80E-10 C 14 1.5896E-22 30.44E-11 0.0000E+00 00.00E+00 C 14 1.1631E-14 21.42E-09 C 14 1.1631E-13 35.69E-08 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.1654E-11 Total 5.7342E-13 1 Y 89m 4.6930E-11 90.85E+00 Y 89m 3.7724E-13 65.79E+00 2 Rb 86m 3.9964E-12 77.37E-01 N 16 9.4427E-14 16.47E+00 3 Y 88 5.1420E-13 99.55E-02 Rb 86m 7.2897E-14 12.71E+00 4 N 16 1.6287E-13 31.53E-02 Y 90 1.2481E-14 21.77E-01 5 Y 90m 4.8325E-14 93.55E-03 Rb 86 6.0637E-15 10.57E-01 6 Sr 87m 1.0881E-15 21.06E-04 Sr 89 5.3484E-15 93.27E-02 7 Rb 86 8.6663E-16 16.78E-04 Y 90m 3.5329E-15 61.61E-02 8 Y 90 3.8524E-17 74.58E-06 Y 88 1.2084E-15 21.07E-02 9 Sr 89 7.9508E-19 15.39E-07 Sr 87m 2.2570E-16 39.36E-03 10 0.0000E+00 00.00E+00 H 3 7.2341E-22 12.62E-08 11 0.0000E+00 00.00E+00 C 14 1.5896E-22 27.72E-09 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 3.72744E+05 +/- 4.78E+04 Bq. Error is 1.28E+01 % of the total. Total Heat Production is 5.22277E-11 +/- 6.77E-12 kW. Error is 1.30E+01 % of the total. Total Gamma Dose Rate is 8.31542E-02 +/- 1.09E-02 Sv/hr. Error is 1.31E+01 % of the total. Total Ingestion Dose is 5.42956E-05 +/- 7.31E-06 Sv. Error is 1.35E+01 % of the total. Total Inhalation Dose is 3.25865E-05 +/- 3.77E-06 Sv. Error is 1.16E+01 % of the total. Total Gamma Heat Prod is 5.16542E-11 +/- 6.71E-12 kW. Error is 1.30E+01 % of the total. Total Beta Heat Prod is 5.73424E-13 +/- 5.81E-14 kW. Error is 1.01E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 7.34302E+06 1.03E+06 3.250E+05 4.57E+04 4.731E-11 6.65E-12 7.689E-02 1.08E-02 5.199E-05 7.31E-06 2.665E-05 3.75E-06 1.406E+01 N 16 2.26258E+03 0.00E+00 2.200E+02 0.00E+00 2.573E-13 0.00E+00 3.002E-04 0.00E+00 1.606E-10 0.00E+00 1.210E-10 0.00E+00 0.000E+00 Rb 86m 4.02027E+06 1.24E+06 4.568E+04 1.41E+04 4.069E-12 1.26E-12 4.930E-03 1.52E-03 1.370E-07 4.24E-08 2.238E-08 6.92E-09 3.093E+01 Y 88 1.58267E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.86674E+06 4.40E+06 4.748E+02 2.66E+02 5.186E-14 2.90E-14 5.106E-05 2.86E-05 8.072E-08 4.52E-08 4.748E-08 2.66E-08 5.596E+01 Rb 86 1.34010E+08 3.40E+07 5.768E+01 1.46E+01 6.930E-15 1.76E-15 1.528E-06 3.87E-07 1.615E-07 4.09E-08 5.364E-08 1.36E-08 2.534E+01 Y 90 2.78244E+07 1.55E+07 8.371E+01 4.67E+01 1.252E-14 6.99E-15 6.817E-13 3.80E-13 2.260E-07 1.26E-07 1.256E-07 7.01E-08 5.581E+01 Sr 89 3.59932E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.09530E+05 2.20E+05 2.116E+01 1.50E+01 1.314E-15 9.33E-16 1.032E-06 7.33E-07 6.349E-10 4.51E-10 4.444E-10 3.16E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 6 * * * COOLING TIME IS 2.7000E+01 SECS * * * ELAPSED TIME IS 2.083 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.35070E+08 1.927E-14 5.813E+01 6.112E-15 0.00E+00 8.735E-16 1.540E-06 1.628E-07 5.406E-08 1.610E+06 Rb 86m 2.95810E+06 4.220E-16 3.361E+04 5.364E-14 0.00E+00 2.941E-12 3.628E-03 1.008E-07 1.647E-08 6.100E+01 Sr 87m 3.08959E+05 4.459E-17 2.112E+01 2.253E-16 0.00E+00 1.086E-15 1.030E-06 6.337E-10 4.436E-10 1.014E+04 Sr 89 3.59931E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58267E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m 2.22284E+06 3.282E-16 9.837E+04 1.142E-13 0.00E+00 1.421E-11 2.328E-02 1.574E-05 8.066E-06 1.566E+01 Y 90 2.78349E+07 4.156E-15 8.374E+01 1.249E-14 0.00E+00 3.854E-17 6.820E-13 2.261E-07 1.256E-07 2.304E+05 Y 90m 7.85393E+06 1.173E-15 4.740E+02 3.527E-15 0.00E+00 4.825E-14 5.098E-05 8.059E-08 4.740E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 10 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 3.61803E-06 0.00000E+00 3.31880E-08 2.98775E-06 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.389814E+03 GAMMA BECQUERELS = 1.324772E+05 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.33867E+05 Bq 1.81263E-05 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.33867E+05 Bq 1.81263E-05 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 1.96740E-13 kW TOTAL GAMMA HEAT PRODUCTION 1.77115E-11 kW TOTAL HEAT PRODUCTION 1.79083E-11 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 1.79083E-11 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 1.80064E-05 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 1.40007E-05 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 1.80064E-05 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 1.40007E-05 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 2.0596E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9777E+03 6.6052E-21 1.2549E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3810E+08 2.2932E-16 1.9701E-14 1.0079E-08 5.9749E-14 4.9619E-07 2.9414E-12 0.0000E+00 0.0000E+00 38 Sr 1.9485E+09 3.2356E-15 2.8503E-13 9.4021E-10 5.5736E-15 1.8334E-10 1.0869E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.2169E-08 1.3142E-13 2.4914E-06 1.4769E-11 0.0000E+00 0.0000E+00 40 Zr 2.2991E+04 3.8177E-20 3.4323E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.22796E+03 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 1.10547E+05 Total gammas (per cc per second) 7.00921E+05 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 1.17455E-01 Gammas per group (per cc per second) 1.17690E+02 ( 0.010- 0.020 MeV) 2.31459E+01 7.73073E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.31435E+01 1.86660E+03 ( 0.300- 0.400 MeV) 6.74670E+00 9.65742E+01 ( 0.400- 0.600 MeV) 1.85576E+04 1.85948E+05 ( 0.600- 0.800 MeV) 1.04375E+00 7.47027E+00 ( 0.800- 1.000 MeV) 8.96671E+04 4.99147E+05 ( 1.000- 1.220 MeV) 5.45190E+00 2.46072E+01 ( 1.220- 1.440 MeV) 2.63378E-01 9.92125E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17144E+03 5.94476E+03 ( 2.000- 2.500 MeV) 2.06878E-06 4.60649E-06 ( 2.500- 3.000 MeV) 1.99896E+01 3.64174E+01 ( 3.000- 4.000 MeV) 2.68267E-01 3.84005E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 2.79341E-02 Sieverts/hour ( 2.79341E+00 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.3387E+05 Total 1.7908E-11 Total 2.7934E-02 Total 1.8006E-05 Total 1.4001E-05 1 Y 89m 9.8369E+04 73.48E+00 Y 89m 1.4321E-11 79.97E+00 Y 89m 2.3277E-02 83.33E+00 Y 89m 1.5739E-05 87.41E+00 Y 89m 8.0663E-06 57.61E+00 2 Rb 86m 3.3613E+04 25.11E+00 Rb 86m 2.9942E-12 16.72E+00 Rb 86m 3.6276E-03 12.99E+00 Y 88 1.5480E-06 85.97E-01 Y 88 5.2394E-06 37.42E+00 3 Y 88 1.1908E+03 88.95E-02 Y 88 5.1541E-13 28.78E-01 Y 88 9.7594E-04 34.94E-01 Y 90 2.2610E-07 12.56E-01 Sr 89 4.5109E-07 32.22E-01 4 Y 90m 4.7404E+02 35.41E-02 Y 90m 5.1773E-14 28.91E-02 Y 90m 5.0979E-05 18.25E-02 Rb 86 1.6277E-07 90.40E-02 Y 90 1.2561E-07 89.72E-02 5 Y 90 8.3740E+01 62.55E-03 Y 90 1.2524E-14 69.94E-03 Rb 86 1.5404E-06 55.14E-04 Sr 89 1.4846E-07 82.45E-02 Rb 86 5.4064E-08 38.62E-02 6 Rb 86 5.8133E+01 43.43E-03 Rb 86 6.9852E-15 39.01E-03 Sr 87m 1.0304E-06 36.89E-04 Rb 86m 1.0084E-07 56.00E-02 Y 90m 4.7404E-08 33.86E-02 7 Sr 89 5.7100E+01 42.65E-03 Sr 89 5.3492E-15 29.87E-03 Sr 89 1.3027E-09 46.63E-07 Y 90m 8.0588E-08 44.75E-02 Rb 86m 1.6470E-08 11.76E-02 8 Sr 87m 2.1125E+01 15.78E-03 Sr 87m 1.3114E-15 73.23E-04 Y 90 6.8196E-13 24.41E-10 Sr 87m 6.3374E-10 35.20E-04 Sr 87m 4.4362E-10 31.69E-04 9 H 3 7.9111E-04 59.10E-08 H 3 7.2341E-22 40.40E-10 0.0000E+00 00.00E+00 H 3 3.3227E-14 18.45E-08 H 3 2.0569E-13 14.69E-07 10 C 14 2.0054E-05 14.98E-09 C 14 1.5896E-22 88.76E-11 0.0000E+00 00.00E+00 C 14 1.1631E-14 64.59E-09 C 14 1.1631E-13 83.08E-08 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 1.7712E-11 Total 1.9674E-13 1 Y 89m 1.4207E-11 80.21E+00 Y 89m 1.1420E-13 58.04E+00 2 Rb 86m 2.9405E-12 16.60E+00 Rb 86m 5.3638E-14 27.26E+00 3 Y 88 5.1420E-13 29.03E-01 Y 90 1.2486E-14 63.46E-01 4 Y 90m 4.8246E-14 27.24E-02 Rb 86 6.1117E-15 31.06E-01 5 Sr 87m 1.0861E-15 61.32E-04 Sr 89 5.3484E-15 27.18E-01 6 Rb 86 8.7349E-16 49.32E-04 Y 90m 3.5271E-15 17.93E-01 7 Y 90 3.8538E-17 21.76E-05 Y 88 1.2084E-15 61.42E-02 8 Sr 89 7.9508E-19 44.89E-07 Sr 87m 2.2528E-16 11.45E-02 9 0.0000E+00 00.00E+00 H 3 7.2341E-22 36.77E-08 10 0.0000E+00 00.00E+00 C 14 1.5896E-22 80.80E-09 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.33867E+05 +/- 1.73E+04 Bq. Error is 1.29E+01 % of the total. Total Heat Production is 1.79083E-11 +/- 2.22E-12 kW. Error is 1.24E+01 % of the total. Total Gamma Dose Rate is 2.79341E-02 +/- 3.46E-03 Sv/hr. Error is 1.24E+01 % of the total. Total Ingestion Dose is 1.80064E-05 +/- 2.22E-06 Sv. Error is 1.23E+01 % of the total. Total Inhalation Dose is 1.40007E-05 +/- 1.21E-06 Sv. Error is 8.63E+00 % of the total. Total Gamma Heat Prod is 1.77115E-11 +/- 2.19E-12 kW. Error is 1.24E+01 % of the total. Total Beta Heat Prod is 1.96740E-13 +/- 2.43E-14 kW. Error is 1.24E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 2.22284E+06 3.12E+05 9.837E+04 1.38E+04 1.432E-11 2.01E-12 2.328E-02 3.27E-03 1.574E-05 2.21E-06 8.066E-06 1.13E-06 1.406E+01 Rb 86m 2.95810E+06 9.15E+05 3.361E+04 1.04E+04 2.994E-12 9.26E-13 3.628E-03 1.12E-03 1.008E-07 3.12E-08 1.647E-08 5.09E-09 3.093E+01 Y 88 1.58267E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.85393E+06 4.39E+06 4.740E+02 2.65E+02 5.177E-14 2.90E-14 5.098E-05 2.85E-05 8.059E-08 4.51E-08 4.740E-08 2.65E-08 5.596E+01 Rb 86 1.35070E+08 3.42E+07 5.813E+01 1.47E+01 6.985E-15 1.77E-15 1.540E-06 3.90E-07 1.628E-07 4.12E-08 5.406E-08 1.37E-08 2.534E+01 Y 90 2.78349E+07 1.55E+07 8.374E+01 4.67E+01 1.252E-14 6.99E-15 6.820E-13 3.81E-13 2.261E-07 1.26E-07 1.256E-07 7.01E-08 5.581E+01 Sr 89 3.59931E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.08959E+05 2.19E+05 2.112E+01 1.50E+01 1.311E-15 9.31E-16 1.030E-06 7.32E-07 6.337E-10 4.50E-10 4.436E-10 3.15E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 7 * * * COOLING TIME IS 3.7000E+01 SECS * * * ELAPSED TIME IS 2.700 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.36083E+08 1.941E-14 5.857E+01 6.158E-15 0.00E+00 8.800E-16 1.552E-06 1.640E-07 5.447E-08 1.610E+06 Rb 86m 1.94277E+06 2.772E-16 2.208E+04 3.523E-14 0.00E+00 1.931E-12 2.383E-03 6.623E-08 1.082E-08 6.100E+01 Sr 87m 3.08179E+05 4.447E-17 2.107E+01 2.247E-16 0.00E+00 1.083E-15 1.028E-06 6.321E-10 4.425E-10 1.014E+04 Sr 89 3.59929E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58267E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m 4.32509E+05 6.385E-17 1.914E+04 2.222E-14 0.00E+00 2.764E-12 4.529E-03 3.062E-06 1.569E-06 1.566E+01 Y 90 2.78493E+07 4.158E-15 8.378E+01 1.249E-14 0.00E+00 3.856E-17 6.823E-13 2.262E-07 1.257E-07 2.304E+05 Y 90m 7.83641E+06 1.170E-15 4.730E+02 3.519E-15 0.00E+00 4.814E-14 5.087E-05 8.041E-08 4.730E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 10 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 1.16487E-06 0.00000E+00 1.45743E-08 8.87275E-07 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.390289E+03 GAMMA BECQUERELS = 4.170991E+04 0 TOTAL ACTIVITY FOR ALL MATERIALS 4.31002E+04 Bq 5.83600E-06 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 4.31002E+04 Bq 5.83600E-06 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 8.63973E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.25981E-12 kW TOTAL HEAT PRODUCTION 5.34621E-12 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.34621E-12 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 5.29635E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 7.49864E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 5.29635E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 7.49864E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 2.2791E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9904E+03 6.6262E-21 1.2589E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3810E+08 2.2932E-16 1.9701E-14 6.9812E-09 4.1385E-14 3.2593E-07 1.9321E-12 0.0000E+00 0.0000E+00 38 Sr 1.9486E+09 3.2357E-15 2.8503E-13 9.4011E-10 5.5730E-15 1.8288E-10 1.0841E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 6.6530E-09 3.9440E-14 5.6116E-07 3.3266E-12 0.0000E+00 0.0000E+00 40 Zr 2.6091E+04 4.3324E-20 3.8951E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 5.39250E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.28292E+04 Total gammas (per cc per second) 2.37648E+05 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 7.50916E-02 Gammas per group (per cc per second) 7.52418E+01 ( 0.010- 0.020 MeV) 1.53780E+01 5.13625E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.29357E+01 1.86243E+03 ( 0.300- 0.400 MeV) 6.72965E+00 9.63302E+01 ( 0.400- 0.600 MeV) 1.22592E+04 1.22837E+05 ( 0.600- 0.800 MeV) 1.04142E+00 7.45360E+00 ( 0.800- 1.000 MeV) 1.82561E+04 1.01626E+05 ( 1.000- 1.220 MeV) 5.49279E+00 2.47918E+01 ( 1.220- 1.440 MeV) 2.63378E-01 9.92122E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17143E+03 5.94474E+03 ( 2.000- 2.500 MeV) 2.06985E-06 4.60888E-06 ( 2.500- 3.000 MeV) 1.99896E+01 3.64173E+01 ( 3.000- 4.000 MeV) 2.68266E-01 3.84004E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 7.94100E-03 Sieverts/hour ( 7.94100E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 4.3100E+04 Total 5.3462E-12 Total 7.9410E-03 Total 5.2964E-06 Total 7.4986E-06 1 Rb 86m 2.2076E+04 51.22E+00 Y 89m 2.7865E-12 52.12E+00 Y 89m 4.5291E-03 57.03E+00 Y 89m 3.0624E-06 57.82E+00 Y 88 5.2394E-06 69.87E+00 2 Y 89m 1.9140E+04 44.41E+00 Rb 86m 1.9665E-12 36.78E+00 Rb 86m 2.3825E-03 30.00E+00 Y 88 1.5480E-06 29.23E+00 Y 89m 1.5695E-06 20.93E+00 3 Y 88 1.1908E+03 27.63E-01 Y 88 5.1540E-13 96.41E-01 Y 88 9.7593E-04 12.29E+00 Y 90 2.2622E-07 42.71E-01 Sr 89 4.5109E-07 60.16E-01 4 Y 90m 4.7299E+02 10.97E-01 Y 90m 5.1658E-14 96.63E-02 Y 90m 5.0866E-05 64.05E-02 Rb 86 1.6399E-07 30.96E-01 Y 90 1.2568E-07 16.76E-01 5 Y 90 8.3783E+01 19.44E-02 Y 90 1.2531E-14 23.44E-02 Rb 86 1.5519E-06 19.54E-03 Sr 89 1.4846E-07 28.03E-01 Rb 86 5.4469E-08 72.64E-02 6 Rb 86 5.8569E+01 13.59E-02 Rb 86 7.0376E-15 13.16E-02 Sr 87m 1.0278E-06 12.94E-03 Y 90m 8.0408E-08 15.18E-01 Y 90m 4.7299E-08 63.08E-02 7 Sr 89 5.7100E+01 13.25E-02 Sr 89 5.3491E-15 10.01E-02 Sr 89 1.3027E-09 16.40E-06 Rb 86m 6.6227E-08 12.50E-01 Rb 86m 1.0817E-08 14.43E-02 8 Sr 87m 2.1071E+01 48.89E-03 Sr 87m 1.3080E-15 24.47E-03 Y 90 6.8232E-13 85.92E-10 Sr 87m 6.3214E-10 11.94E-03 Sr 87m 4.4250E-10 59.01E-04 9 H 3 7.9111E-04 18.36E-07 H 3 7.2341E-22 13.53E-09 0.0000E+00 00.00E+00 H 3 3.3227E-14 62.74E-08 H 3 2.0569E-13 27.43E-07 10 C 14 2.0054E-05 46.53E-09 C 14 1.5896E-22 29.73E-10 0.0000E+00 00.00E+00 C 14 1.1631E-14 21.96E-08 C 14 1.1631E-13 15.51E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.2598E-12 Total 8.6397E-14 1 Y 89m 2.7642E-12 52.55E+00 Rb 86m 3.5227E-14 40.77E+00 2 Rb 86m 1.9312E-12 36.72E+00 Y 89m 2.2220E-14 25.72E+00 3 Y 88 5.1420E-13 97.76E-01 Y 90 1.2492E-14 14.46E+00 4 Y 90m 4.8139E-14 91.52E-02 Rb 86 6.1575E-15 71.27E-01 5 Sr 87m 1.0833E-15 20.60E-03 Sr 89 5.3483E-15 61.90E-01 6 Rb 86 8.8005E-16 16.73E-03 Y 90m 3.5193E-15 40.73E-01 7 Y 90 3.8558E-17 73.31E-05 Y 88 1.2084E-15 13.99E-01 8 Sr 89 7.9507E-19 15.12E-06 Sr 87m 2.2471E-16 26.01E-02 9 0.0000E+00 00.00E+00 H 3 7.2341E-22 83.73E-08 10 0.0000E+00 00.00E+00 C 14 1.5896E-22 18.40E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 4.31002E+04 +/- 7.34E+03 Bq. Error is 1.70E+01 % of the total. Total Heat Production is 5.34621E-12 +/- 7.25E-13 kW. Error is 1.36E+01 % of the total. Total Gamma Dose Rate is 7.94100E-03 +/- 9.77E-04 Sv/hr. Error is 1.23E+01 % of the total. Total Ingestion Dose is 5.29635E-06 +/- 4.70E-07 Sv. Error is 8.87E+00 % of the total. Total Inhalation Dose is 7.49864E-06 +/- 4.72E-07 Sv. Error is 6.29E+00 % of the total. Total Gamma Heat Prod is 5.25981E-12 +/- 7.14E-13 kW. Error is 1.36E+01 % of the total. Total Beta Heat Prod is 8.63973E-14 +/- 1.37E-14 kW. Error is 1.58E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 4.32509E+05 6.08E+04 1.914E+04 2.69E+03 2.786E-12 3.92E-13 4.529E-03 6.37E-04 3.062E-06 4.31E-07 1.569E-06 2.21E-07 1.406E+01 Rb 86m 1.94277E+06 6.01E+05 2.208E+04 6.83E+03 1.966E-12 6.08E-13 2.383E-03 7.37E-04 6.623E-08 2.05E-08 1.082E-08 3.35E-09 3.093E+01 Y 88 1.58267E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.83641E+06 4.39E+06 4.730E+02 2.65E+02 5.166E-14 2.89E-14 5.087E-05 2.85E-05 8.041E-08 4.50E-08 4.730E-08 2.65E-08 5.596E+01 Rb 86 1.36083E+08 3.45E+07 5.857E+01 1.48E+01 7.038E-15 1.78E-15 1.552E-06 3.93E-07 1.640E-07 4.16E-08 5.447E-08 1.38E-08 2.534E+01 Y 90 2.78493E+07 1.55E+07 8.378E+01 4.68E+01 1.253E-14 6.99E-15 6.823E-13 3.81E-13 2.262E-07 1.26E-07 1.257E-07 7.01E-08 5.581E+01 Sr 89 3.59929E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.08179E+05 2.19E+05 2.107E+01 1.50E+01 1.308E-15 9.29E-16 1.028E-06 7.30E-07 6.321E-10 4.49E-10 4.425E-10 3.14E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 8 * * * COOLING TIME IS 3.4000E+01 SECS * * * ELAPSED TIME IS 3.267 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.36704E+08 1.950E-14 5.884E+01 6.186E-15 0.00E+00 8.841E-16 1.559E-06 1.647E-07 5.472E-08 1.610E+06 Rb 86m 1.32018E+06 1.883E-16 1.500E+04 2.394E-14 0.00E+00 1.312E-12 1.619E-03 4.500E-08 7.351E-09 6.100E+01 Sr 87m 3.07463E+05 4.437E-17 2.102E+01 2.242E-16 0.00E+00 1.081E-15 1.025E-06 6.307E-10 4.415E-10 1.014E+04 Sr 89 3.59927E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58266E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m 9.59317E+04 1.416E-17 4.245E+03 4.928E-15 0.00E+00 6.131E-13 1.005E-03 6.793E-07 3.481E-07 1.566E+01 Y 90 2.78625E+07 4.160E-15 8.382E+01 1.250E-14 0.00E+00 3.858E-17 6.826E-13 2.263E-07 1.257E-07 2.304E+05 Y 90m 7.82035E+06 1.168E-15 4.720E+02 3.512E-15 0.00E+00 4.804E-14 5.076E-05 8.024E-08 4.720E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 10 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 5.71086E-07 0.00000E+00 9.75754E-09 4.19986E-07 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.390593E+03 GAMMA BECQUERELS = 1.973959E+04 0 TOTAL ACTIVITY FOR ALL MATERIALS 2.11302E+04 Bq 2.86114E-06 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 2.11302E+04 Bq 2.86114E-06 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 5.78432E-14 kW TOTAL GAMMA HEAT PRODUCTION 2.48970E-12 kW TOTAL HEAT PRODUCTION 2.54754E-12 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 2.54754E-12 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.89264E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 6.27399E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.89264E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 6.27399E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 2.4808E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9951E+03 6.6340E-21 1.2603E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3810E+08 2.2931E-16 1.9700E-14 5.0816E-09 3.0124E-14 2.2153E-07 1.3132E-12 0.0000E+00 0.0000E+00 38 Sr 1.9486E+09 3.2357E-15 2.8504E-13 9.4002E-10 5.5725E-15 1.8246E-10 1.0816E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 3.7360E-09 2.2147E-14 1.9828E-07 1.1754E-12 0.0000E+00 0.0000E+00 40 Zr 2.8940E+04 4.8056E-20 4.3205E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 3.61029E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 1.55395E+04 Total gammas (per cc per second) 1.23481E+05 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 6.14007E-02 Gammas per group (per cc per second) 6.15235E+01 ( 0.010- 0.020 MeV) 1.32323E+01 4.41960E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.27452E+01 1.85861E+03 ( 0.300- 0.400 MeV) 6.71403E+00 9.61065E+01 ( 0.400- 0.600 MeV) 8.39695E+03 8.41374E+04 ( 0.600- 0.800 MeV) 1.03929E+00 7.43832E+00 ( 0.800- 1.000 MeV) 4.83104E+03 2.68928E+04 ( 1.000- 1.220 MeV) 5.51784E+00 2.49048E+01 ( 1.220- 1.440 MeV) 2.63377E-01 9.92119E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17143E+03 5.94473E+03 ( 2.000- 2.500 MeV) 2.07084E-06 4.61106E-06 ( 2.500- 3.000 MeV) 1.99895E+01 3.64173E+01 ( 3.000- 4.000 MeV) 2.68266E-01 3.84003E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 3.65285E-03 Sieverts/hour ( 3.65285E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 2.1130E+04 Total 2.5475E-12 Total 3.6528E-03 Total 2.8926E-06 Total 6.2740E-06 1 Rb 86m 1.5001E+04 70.99E+00 Rb 86m 1.3363E-12 52.45E+00 Rb 86m 1.6190E-03 44.32E+00 Y 88 1.5480E-06 53.51E+00 Y 88 5.2393E-06 83.51E+00 2 Y 89m 4.2453E+03 20.09E+00 Y 89m 6.1804E-13 24.26E+00 Y 89m 1.0046E-03 27.50E+00 Y 89m 6.7925E-07 23.48E+00 Sr 89 4.5109E-07 71.90E-01 3 Y 88 1.1908E+03 56.35E-01 Y 88 5.1540E-13 20.23E+00 Y 88 9.7593E-04 26.72E+00 Y 90 2.2632E-07 78.24E-01 Y 89m 3.4812E-07 55.49E-01 4 Y 90m 4.7202E+02 22.34E-01 Y 90m 5.1552E-14 20.24E-01 Y 90m 5.0761E-05 13.90E-01 Rb 86 1.6474E-07 56.95E-01 Y 90 1.2573E-07 20.04E-01 5 Y 90 8.3823E+01 39.67E-02 Y 90 1.2537E-14 49.21E-02 Rb 86 1.5590E-06 42.68E-03 Sr 89 1.4846E-07 51.32E-01 Rb 86 5.4718E-08 87.21E-02 6 Rb 86 5.8836E+01 27.84E-02 Rb 86 7.0697E-15 27.75E-02 Sr 87m 1.0254E-06 28.07E-03 Y 90m 8.0243E-08 27.74E-01 Y 90m 4.7202E-08 75.23E-02 7 Sr 89 5.7100E+01 27.02E-02 Sr 89 5.3491E-15 21.00E-02 Sr 89 1.3027E-09 35.66E-06 Rb 86m 4.5004E-08 15.56E-01 Rb 86m 7.3506E-09 11.72E-02 8 Sr 87m 2.1022E+01 99.49E-03 Sr 87m 1.3050E-15 51.23E-03 Y 90 6.8264E-13 18.69E-09 Sr 87m 6.3067E-10 21.80E-03 Sr 87m 4.4147E-10 70.37E-04 9 H 3 7.9111E-04 37.44E-07 H 3 7.2341E-22 28.40E-09 0.0000E+00 00.00E+00 H 3 3.3227E-14 11.49E-07 H 3 2.0569E-13 32.78E-07 10 C 14 2.0054E-05 94.91E-09 C 14 1.5896E-22 62.40E-10 0.0000E+00 00.00E+00 C 14 1.1631E-14 40.21E-08 C 14 1.1631E-13 18.54E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 2.4897E-12 Total 5.7843E-14 1 Rb 86m 1.3123E-12 52.71E+00 Rb 86m 2.3938E-14 41.38E+00 2 Y 89m 6.1311E-13 24.63E+00 Y 90 1.2498E-14 21.61E+00 3 Y 88 5.1419E-13 20.65E+00 Rb 86 6.1856E-15 10.69E+00 4 Y 90m 4.8040E-14 19.30E-01 Sr 89 5.3483E-15 92.46E-01 5 Sr 87m 1.0808E-15 43.41E-03 Y 89m 4.9284E-15 85.20E-01 6 Rb 86 8.8406E-16 35.51E-03 Y 90m 3.5121E-15 60.72E-01 7 Y 90 3.8577E-17 15.49E-04 Y 88 1.2084E-15 20.89E-01 8 Sr 89 7.9507E-19 31.93E-06 Sr 87m 2.2419E-16 38.76E-02 9 0.0000E+00 00.00E+00 H 3 7.2341E-22 12.51E-07 10 0.0000E+00 00.00E+00 C 14 1.5896E-22 27.48E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 2.11302E+04 +/- 4.69E+03 Bq. Error is 2.22E+01 % of the total. Total Heat Production is 2.54754E-12 +/- 4.25E-13 kW. Error is 1.67E+01 % of the total. Total Gamma Dose Rate is 3.65285E-03 +/- 5.26E-04 Sv/hr. Error is 1.44E+01 % of the total. Total Ingestion Dose is 2.89264E-06 +/- 2.10E-07 Sv. Error is 7.27E+00 % of the total. Total Inhalation Dose is 6.27399E-06 +/- 4.20E-07 Sv. Error is 6.69E+00 % of the total. Total Gamma Heat Prod is 2.48970E-12 +/- 4.17E-13 kW. Error is 1.68E+01 % of the total. Total Beta Heat Prod is 5.78432E-14 +/- 1.07E-14 kW. Error is 1.85E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 9.59317E+04 1.35E+04 4.245E+03 5.97E+02 6.180E-13 8.69E-14 1.005E-03 1.41E-04 6.793E-07 9.55E-08 3.481E-07 4.89E-08 1.406E+01 Rb 86m 1.32018E+06 4.08E+05 1.500E+04 4.64E+03 1.336E-12 4.13E-13 1.619E-03 5.01E-04 4.500E-08 1.39E-08 7.351E-09 2.27E-09 3.093E+01 Y 88 1.58266E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.82035E+06 4.38E+06 4.720E+02 2.64E+02 5.155E-14 2.88E-14 5.076E-05 2.84E-05 8.024E-08 4.49E-08 4.720E-08 2.64E-08 5.596E+01 Rb 86 1.36704E+08 3.46E+07 5.884E+01 1.49E+01 7.070E-15 1.79E-15 1.559E-06 3.95E-07 1.647E-07 4.17E-08 5.472E-08 1.39E-08 2.534E+01 Y 90 2.78625E+07 1.56E+07 8.382E+01 4.68E+01 1.254E-14 7.00E-15 6.826E-13 3.81E-13 2.263E-07 1.26E-07 1.257E-07 7.02E-08 5.581E+01 Sr 89 3.59927E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.07463E+05 2.18E+05 2.102E+01 1.49E+01 1.305E-15 9.27E-16 1.025E-06 7.28E-07 6.307E-10 4.48E-10 4.415E-10 3.13E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 9 * * * COOLING TIME IS 5.3000E+01 SECS * * * ELAPSED TIME IS 4.150 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * * * * * * * * * * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37298E+08 1.959E-14 5.909E+01 6.212E-15 0.00E+00 8.879E-16 1.566E-06 1.655E-07 5.496E-08 1.610E+06 Rb 86m 7.22900E+05 1.031E-16 8.214E+03 1.311E-14 0.00E+00 7.186E-13 8.865E-04 2.464E-08 4.025E-09 6.100E+01 Sr 87m 3.06351E+05 4.421E-17 2.095E+01 2.234E-16 0.00E+00 1.077E-15 1.022E-06 6.284E-10 4.399E-10 1.014E+04 Sr 89 3.59924E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58265E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 89m 9.04734E+03 1.336E-18 4.004E+02 4.648E-16 0.00E+00 5.782E-14 9.474E-05 6.406E-08 3.283E-08 1.566E+01 Y 90 2.78831E+07 4.163E-15 8.388E+01 1.251E-14 0.00E+00 3.860E-17 6.831E-13 2.265E-07 1.258E-07 2.304E+05 Y 90m 7.79537E+06 1.164E-15 4.705E+02 3.501E-15 0.00E+00 4.789E-14 5.060E-05 7.999E-08 4.705E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 10 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 2.83703E-07 0.00000E+00 7.18170E-09 2.26131E-07 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.390905E+03 GAMMA BECQUERELS = 9.106122E+03 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.04970E+04 Bq 1.42135E-06 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.04970E+04 Bq 1.42135E-06 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 4.25735E-14 kW TOTAL GAMMA HEAT PRODUCTION 1.34052E-12 kW TOTAL HEAT PRODUCTION 1.38309E-12 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 1.38309E-12 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.25771E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.95553E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.25770E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.95553E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 2.7952E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9975E+03 6.6381E-21 1.2611E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3809E+08 2.2931E-16 1.9700E-14 3.2592E-09 1.9320E-14 1.2137E-07 7.1950E-13 0.0000E+00 0.0000E+00 38 Sr 1.9487E+09 3.2359E-15 2.8505E-13 9.3988E-10 5.5716E-15 1.8180E-10 1.0777E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9827E-09 1.7681E-14 1.0458E-07 6.1994E-13 0.0000E+00 0.0000E+00 40 Zr 3.3385E+04 5.5437E-20 4.9841E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 2.65723E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 8.36685E+03 Total gammas (per cc per second) 6.66279E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 5.20697E-02 Gammas per group (per cc per second) 5.21738E+01 ( 0.010- 0.020 MeV) 1.19849E+01 4.00295E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.24490E+01 1.85268E+03 ( 0.300- 0.400 MeV) 6.68974E+00 9.57588E+01 ( 0.400- 0.600 MeV) 4.69144E+03 4.70082E+04 ( 0.600- 0.800 MeV) 1.03597E+00 7.41456E+00 ( 0.800- 1.000 MeV) 1.36547E+03 7.60114E+03 ( 1.000- 1.220 MeV) 5.54182E+00 2.50131E+01 ( 1.220- 1.440 MeV) 2.63376E-01 9.92115E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17142E+03 5.94470E+03 ( 2.000- 2.500 MeV) 2.07236E-06 4.61446E-06 ( 2.500- 3.000 MeV) 1.99894E+01 3.64171E+01 ( 3.000- 4.000 MeV) 2.68264E-01 3.84001E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 2.01038E-03 Sieverts/hour ( 2.01038E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.0497E+04 Total 1.3831E-12 Total 2.0104E-03 Total 2.2577E-06 Total 5.9555E-06 1 Rb 86m 8.2144E+03 78.25E+00 Rb 86m 7.3172E-13 52.90E+00 Y 88 9.7593E-04 48.54E+00 Y 88 1.5480E-06 68.56E+00 Y 88 5.2393E-06 87.97E+00 2 Y 88 1.1908E+03 11.34E+00 Y 88 5.1540E-13 37.26E+00 Rb 86m 8.8652E-04 44.10E+00 Y 90 2.2649E-07 10.03E+00 Sr 89 4.5108E-07 75.74E-01 3 Y 90m 4.7051E+02 44.82E-01 Y 89m 5.8288E-14 42.14E-01 Y 89m 9.4741E-05 47.13E-01 Rb 86 1.6546E-07 73.29E-01 Y 90 1.2583E-07 21.13E-01 4 Y 89m 4.0038E+02 38.14E-01 Y 90m 5.1387E-14 37.15E-01 Y 90m 5.0599E-05 25.17E-01 Sr 89 1.4846E-07 65.76E-01 Rb 86 5.4956E-08 92.28E-02 5 Y 90 8.3885E+01 79.91E-02 Y 90 1.2546E-14 90.71E-02 Rb 86 1.5658E-06 77.88E-03 Y 90m 7.9987E-08 35.43E-01 Y 90m 4.7051E-08 79.00E-02 6 Rb 86 5.9092E+01 56.29E-02 Rb 86 7.1004E-15 51.34E-02 Sr 87m 1.0217E-06 50.82E-03 Y 89m 6.4061E-08 28.37E-01 Y 89m 3.2831E-08 55.13E-02 7 Sr 89 5.7099E+01 54.40E-02 Sr 89 5.3491E-15 38.67E-02 Sr 89 1.3027E-09 64.80E-06 Rb 86m 2.4643E-08 10.92E-01 Rb 86m 4.0250E-09 67.58E-03 8 Sr 87m 2.0946E+01 19.95E-02 Sr 87m 1.3003E-15 94.01E-03 Y 90 6.8314E-13 33.98E-09 Sr 87m 6.2839E-10 27.83E-03 Sr 87m 4.3987E-10 73.86E-04 9 H 3 7.9111E-04 75.37E-07 H 3 7.2341E-22 52.30E-09 0.0000E+00 00.00E+00 H 3 3.3227E-14 14.72E-07 H 3 2.0569E-13 34.54E-07 10 C 14 2.0054E-05 19.10E-08 C 14 1.5896E-22 11.49E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 51.52E-08 C 14 1.1631E-13 19.53E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 1.3405E-12 Total 4.2574E-14 1 Rb 86m 7.1861E-13 53.61E+00 Rb 86m 1.3108E-14 30.79E+00 2 Y 88 5.1419E-13 38.36E+00 Y 90 1.2507E-14 29.38E+00 3 Y 89m 5.7823E-14 43.13E-01 Rb 86 6.2125E-15 14.59E+00 4 Y 90m 4.7886E-14 35.72E-01 Sr 89 5.3483E-15 12.56E+00 5 Sr 87m 1.0769E-15 80.34E-03 Y 90m 3.5008E-15 82.23E-01 6 Rb 86 8.8790E-16 66.24E-03 Y 88 1.2084E-15 28.38E-01 7 Y 90 3.8605E-17 28.80E-04 Y 89m 4.6480E-16 10.92E-01 8 Sr 89 7.9506E-19 59.31E-06 Sr 87m 2.2338E-16 52.47E-02 9 0.0000E+00 00.00E+00 H 3 7.2341E-22 16.99E-07 10 0.0000E+00 00.00E+00 C 14 1.5896E-22 37.34E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.04970E+04 +/- 2.56E+03 Bq. Error is 2.44E+01 % of the total. Total Heat Production is 1.38309E-12 +/- 2.31E-13 kW. Error is 1.67E+01 % of the total. Total Gamma Dose Rate is 2.01038E-03 +/- 2.85E-04 Sv/hr. Error is 1.42E+01 % of the total. Total Ingestion Dose is 2.25771E-06 +/- 1.87E-07 Sv. Error is 8.30E+00 % of the total. Total Inhalation Dose is 5.95553E-06 +/- 4.17E-07 Sv. Error is 7.01E+00 % of the total. Total Gamma Heat Prod is 1.34052E-12 +/- 2.27E-13 kW. Error is 1.69E+01 % of the total. Total Beta Heat Prod is 4.25735E-14 +/- 8.67E-15 kW. Error is 2.04E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 89m 9.04734E+03 1.27E+03 4.004E+02 5.63E+01 5.829E-14 8.19E-15 9.474E-05 1.33E-05 6.406E-08 9.01E-09 3.283E-08 4.62E-09 1.406E+01 Rb 86m 7.22900E+05 2.24E+05 8.214E+03 2.54E+03 7.317E-13 2.26E-13 8.865E-04 2.74E-04 2.464E-08 7.62E-09 4.025E-09 1.24E-09 3.093E+01 Y 88 1.58265E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.79537E+06 4.36E+06 4.705E+02 2.63E+02 5.139E-14 2.88E-14 5.060E-05 2.83E-05 7.999E-08 4.48E-08 4.705E-08 2.63E-08 5.596E+01 Rb 86 1.37298E+08 3.48E+07 5.909E+01 1.50E+01 7.100E-15 1.80E-15 1.566E-06 3.97E-07 1.655E-07 4.19E-08 5.496E-08 1.39E-08 2.534E+01 Y 90 2.78831E+07 1.56E+07 8.388E+01 4.68E+01 1.255E-14 7.00E-15 6.831E-13 3.81E-13 2.265E-07 1.26E-07 1.258E-07 7.02E-08 5.581E+01 Sr 89 3.59924E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.06351E+05 2.18E+05 2.095E+01 1.49E+01 1.300E-15 9.23E-16 1.022E-06 7.25E-07 6.284E-10 4.46E-10 4.399E-10 3.12E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 10 * * * COOLING TIME IS 6.7000E+01 SECS OR 1.1167E+00 MINS * * * ELAPSED TIME IS 5.267 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37679E+08 1.964E-14 5.926E+01 6.230E-15 0.00E+00 8.904E-16 1.570E-06 1.659E-07 5.511E-08 1.610E+06 Rb 86m 3.37613E+05 4.816E-17 3.836E+03 6.122E-15 0.00E+00 3.356E-13 4.140E-04 1.151E-08 1.880E-09 6.100E+01 Sr 87m 3.04951E+05 4.401E-17 2.085E+01 2.224E-16 0.00E+00 1.072E-15 1.017E-06 6.255E-10 4.379E-10 1.014E+04 Sr 89 3.59920E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.951E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58265E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.79089E+07 4.167E-15 8.396E+01 1.252E-14 0.00E+00 3.864E-17 6.838E-13 2.267E-07 1.259E-07 2.304E+05 Y 90m 7.76391E+06 1.159E-15 4.686E+02 3.487E-15 0.00E+00 4.769E-14 5.040E-05 7.966E-08 4.686E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 9 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 1.54510E-07 0.00000E+00 5.92710E-09 1.51735E-07 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.391140E+03 GAMMA BECQUERELS = 4.325713E+03 0 TOTAL ACTIVITY FOR ALL MATERIALS 5.71685E+03 Bq 7.74093E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 5.71685E+03 Bq 7.74093E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 3.51361E-14 kW TOTAL GAMMA HEAT PRODUCTION 8.99495E-13 kW TOTAL HEAT PRODUCTION 9.34631E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 9.34631E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.18084E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.92060E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.18084E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.92060E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 3.1926E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9982E+03 6.6392E-21 1.2613E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3809E+08 2.2930E-16 1.9699E-14 2.0836E-09 1.2352E-14 5.6764E-08 3.3650E-13 0.0000E+00 0.0000E+00 38 Sr 1.9488E+09 3.2360E-15 2.8506E-13 9.3969E-10 5.5706E-15 1.8097E-10 1.0728E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9038E-09 1.7214E-14 9.4790E-08 5.6192E-13 0.0000E+00 0.0000E+00 40 Zr 3.9009E+04 6.4775E-20 5.8236E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 2.19303E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 5.61421E+03 Total gammas (per cc per second) 4.04357E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.67982E-02 Gammas per group (per cc per second) 4.68918E+01 ( 0.010- 0.020 MeV) 1.13407E+01 3.78781E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.20759E+01 1.84520E+03 ( 0.300- 0.400 MeV) 6.65916E+00 9.53212E+01 ( 0.400- 0.600 MeV) 2.30073E+03 2.30533E+04 ( 0.600- 0.800 MeV) 1.03179E+00 7.38464E+00 ( 0.800- 1.000 MeV) 1.00460E+03 5.59226E+03 ( 1.000- 1.220 MeV) 5.55721E+00 2.50826E+01 ( 1.220- 1.440 MeV) 2.63375E-01 9.92110E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17141E+03 5.94467E+03 ( 2.000- 2.500 MeV) 2.07428E-06 4.61874E-06 ( 2.500- 3.000 MeV) 1.99893E+01 3.64169E+01 ( 3.000- 4.000 MeV) 2.68263E-01 3.84000E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.44294E-03 Sieverts/hour ( 1.44294E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 5.7169E+03 Total 9.3463E-13 Total 1.4429E-03 Total 2.1808E-06 Total 5.9206E-06 1 Rb 86m 3.8363E+03 67.11E+00 Y 88 5.1540E-13 55.14E+00 Y 88 9.7592E-04 67.63E+00 Y 88 1.5480E-06 70.98E+00 Y 88 5.2393E-06 88.49E+00 2 Y 88 1.1907E+03 20.83E+00 Rb 86m 3.4173E-13 36.56E+00 Rb 86m 4.1403E-04 28.69E+00 Y 90 2.2670E-07 10.40E+00 Sr 89 4.5108E-07 76.19E-01 3 Y 90m 4.6861E+02 81.97E-01 Y 90m 5.1180E-14 54.76E-01 Y 90m 5.0395E-05 34.93E-01 Rb 86 1.6592E-07 76.08E-01 Y 90 1.2594E-07 21.27E-01 4 Y 90 8.3963E+01 14.69E-01 Y 90 1.2558E-14 13.44E-01 Rb 86 1.5701E-06 10.88E-02 Sr 89 1.4846E-07 68.07E-01 Rb 86 5.5108E-08 93.08E-02 5 Rb 86 5.9256E+01 10.37E-01 Rb 86 7.1201E-15 76.18E-02 Sr 87m 1.0170E-06 70.48E-03 Y 90m 7.9664E-08 36.53E-01 Y 90m 4.6861E-08 79.15E-02 6 Sr 89 5.7098E+01 99.88E-02 Sr 89 5.3490E-15 57.23E-02 Sr 89 1.3027E-09 90.28E-06 Rb 86m 1.1509E-08 52.77E-02 Rb 86m 1.8798E-09 31.75E-03 7 Sr 87m 2.0851E+01 36.47E-02 Sr 87m 1.2943E-15 13.85E-02 Y 90 6.8378E-13 47.39E-09 Sr 87m 6.2552E-10 28.68E-03 Sr 87m 4.3786E-10 73.96E-04 8 H 3 7.9111E-04 13.84E-06 H 3 7.2341E-22 77.40E-09 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.24E-07 H 3 2.0569E-13 34.74E-07 9 C 14 2.0054E-05 35.08E-08 C 14 1.5896E-22 17.01E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.33E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 8.9950E-13 Total 3.5136E-14 1 Y 88 5.1419E-13 57.16E+00 Y 90 1.2519E-14 35.63E+00 2 Rb 86m 3.3561E-13 37.31E+00 Rb 86 6.2297E-15 17.73E+00 3 Y 90m 4.7693E-14 53.02E-01 Rb 86m 6.1218E-15 17.42E+00 4 Sr 87m 1.0720E-15 11.92E-02 Sr 89 5.3482E-15 15.22E+00 5 Rb 86 8.9037E-16 98.99E-03 Y 90m 3.4867E-15 99.23E-01 6 Y 90 3.8641E-17 42.96E-04 Y 88 1.2084E-15 34.39E-01 7 Sr 89 7.9505E-19 88.39E-06 Sr 87m 2.2236E-16 63.28E-02 8 0.0000E+00 00.00E+00 H 3 7.2341E-22 20.59E-07 9 0.0000E+00 00.00E+00 C 14 1.5896E-22 45.24E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 5.71685E+03 +/- 1.22E+03 Bq. Error is 2.13E+01 % of the total. Total Heat Production is 9.34631E-13 +/- 1.16E-13 kW. Error is 1.24E+01 % of the total. Total Gamma Dose Rate is 1.44294E-03 +/- 1.49E-04 Sv/hr. Error is 1.03E+01 % of the total. Total Ingestion Dose is 2.18084E-06 +/- 1.87E-07 Sv. Error is 8.58E+00 % of the total. Total Inhalation Dose is 5.92060E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 8.99495E-13 +/- 1.13E-13 kW. Error is 1.26E+01 % of the total. Total Beta Heat Prod is 3.51361E-14 +/- 7.90E-15 kW. Error is 2.25E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Rb 86m 3.37613E+05 1.04E+05 3.836E+03 1.19E+03 3.417E-13 1.06E-13 4.140E-04 1.28E-04 1.151E-08 3.56E-09 1.880E-09 5.81E-10 3.093E+01 Y 88 1.58265E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.76391E+06 4.34E+06 4.686E+02 2.62E+02 5.118E-14 2.86E-14 5.040E-05 2.82E-05 7.966E-08 4.46E-08 4.686E-08 2.62E-08 5.596E+01 Rb 86 1.37679E+08 3.49E+07 5.926E+01 1.50E+01 7.120E-15 1.80E-15 1.570E-06 3.98E-07 1.659E-07 4.20E-08 5.511E-08 1.40E-08 2.534E+01 Y 90 2.79089E+07 1.56E+07 8.396E+01 4.69E+01 1.256E-14 7.01E-15 6.838E-13 3.82E-13 2.267E-07 1.27E-07 1.259E-07 7.03E-08 5.581E+01 Sr 89 3.59920E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.04951E+05 2.17E+05 2.085E+01 1.48E+01 1.294E-15 9.19E-16 1.017E-06 7.22E-07 6.255E-10 4.44E-10 4.379E-10 3.11E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 11 * * * COOLING TIME IS 6.7000E+01 SECS OR 1.1167E+00 MINS * * * ELAPSED TIME IS 6.383 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37855E+08 1.967E-14 5.933E+01 6.238E-15 0.00E+00 8.915E-16 1.572E-06 1.661E-07 5.518E-08 1.610E+06 Rb 86m 1.57760E+05 2.251E-17 1.793E+03 2.861E-15 0.00E+00 1.568E-13 1.935E-04 5.378E-09 8.784E-10 6.100E+01 Sr 87m 3.03557E+05 4.381E-17 2.076E+01 2.213E-16 0.00E+00 1.067E-15 1.012E-06 6.227E-10 4.359E-10 1.014E+04 Sr 89 3.59916E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.950E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58264E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.79346E+07 4.170E-15 8.404E+01 1.253E-14 0.00E+00 3.868E-17 6.844E-13 2.269E-07 1.261E-07 2.304E+05 Y 90m 7.73257E+06 1.154E-15 4.667E+02 3.473E-15 0.00E+00 4.750E-14 5.019E-05 7.934E-08 4.667E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 9 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 9.92251E-08 0.00000E+00 5.37770E-09 1.21542E-07 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.391286E+03 GAMMA BECQUERELS = 2.280044E+03 0 TOTAL ACTIVITY FOR ALL MATERIALS 3.67133E+03 Bq 4.97118E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 3.67133E+03 Bq 4.97118E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 3.18793E-14 kW TOTAL GAMMA HEAT PRODUCTION 7.20510E-13 kW TOTAL HEAT PRODUCTION 7.52389E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 7.52389E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.17480E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91957E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.17480E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91957E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 3.5901E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6394E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3808E+08 2.2929E-16 1.9699E-14 1.5348E-09 9.0983E-15 2.6605E-08 1.5772E-13 0.0000E+00 0.0000E+00 38 Sr 1.9488E+09 3.2361E-15 2.8507E-13 9.3951E-10 5.5695E-15 1.8014E-10 1.0679E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9034E-09 1.7212E-14 9.4757E-08 5.6173E-13 0.0000E+00 0.0000E+00 40 Zr 4.4637E+04 7.4122E-20 6.6639E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.98975E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 4.49707E+03 Total gammas (per cc per second) 2.91428E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.43935E-02 Gammas per group (per cc per second) 4.44823E+01 ( 0.010- 0.020 MeV) 1.10534E+01 3.69184E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.17043E+01 1.83775E+03 ( 0.300- 0.400 MeV) 6.62873E+00 9.48855E+01 ( 0.400- 0.600 MeV) 1.18430E+03 1.18667E+04 ( 0.600- 0.800 MeV) 1.02762E+00 7.35484E+00 ( 0.800- 1.000 MeV) 1.00459E+03 5.59223E+03 ( 1.000- 1.220 MeV) 5.56431E+00 2.51146E+01 ( 1.220- 1.440 MeV) 2.63373E-01 9.92105E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17140E+03 5.94464E+03 ( 2.000- 2.500 MeV) 2.07619E-06 4.62299E-06 ( 2.500- 3.000 MeV) 1.99892E+01 3.64167E+01 ( 3.000- 4.000 MeV) 2.68262E-01 3.83998E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.22216E-03 Sieverts/hour ( 1.22216E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 3.6713E+03 Total 7.5239E-13 Total 1.2222E-03 Total 2.1748E-06 Total 5.9196E-06 1 Rb 86m 1.7926E+03 48.83E+00 Y 88 5.1540E-13 68.50E+00 Y 88 9.7592E-04 79.85E+00 Y 88 1.5480E-06 71.18E+00 Y 88 5.2393E-06 88.51E+00 2 Y 88 1.1907E+03 32.43E+00 Rb 86m 1.5969E-13 21.22E+00 Rb 86m 1.9347E-04 15.83E+00 Y 90 2.2691E-07 10.43E+00 Sr 89 4.5107E-07 76.20E-01 3 Y 90m 4.6672E+02 12.71E+00 Y 90m 5.0973E-14 67.75E-01 Y 90m 5.0192E-05 41.07E-01 Rb 86 1.6613E-07 76.39E-01 Y 90 1.2606E-07 21.30E-01 4 Y 90 8.4040E+01 22.89E-01 Y 90 1.2569E-14 16.71E-01 Rb 86 1.5721E-06 12.86E-02 Sr 89 1.4845E-07 68.26E-01 Rb 86 5.5179E-08 93.21E-02 5 Rb 86 5.9332E+01 16.16E-01 Rb 86 7.1292E-15 94.75E-02 Sr 87m 1.0124E-06 82.83E-03 Y 90m 7.9342E-08 36.48E-01 Y 90m 4.6672E-08 78.84E-02 6 Sr 89 5.7098E+01 15.55E-01 Sr 89 5.3489E-15 71.09E-02 Sr 89 1.3027E-09 10.66E-05 Rb 86m 5.3779E-09 24.73E-02 Rb 86m 8.7839E-10 14.84E-03 7 Sr 87m 2.0755E+01 56.53E-02 Sr 87m 1.2884E-15 17.12E-02 Y 90 6.8441E-13 56.00E-09 Sr 87m 6.2266E-10 28.63E-03 Sr 87m 4.3586E-10 73.63E-04 8 H 3 7.9111E-04 21.55E-06 H 3 7.2341E-22 96.15E-09 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.28E-07 H 3 2.0569E-13 34.75E-07 9 C 14 2.0054E-05 54.62E-08 C 14 1.5896E-22 21.13E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.48E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 7.2051E-13 Total 3.1879E-14 1 Y 88 5.1419E-13 71.36E+00 Y 90 1.2531E-14 39.31E+00 2 Rb 86m 1.5682E-13 21.77E+00 Rb 86 6.2377E-15 19.57E+00 3 Y 90m 4.7501E-14 65.93E-01 Sr 89 5.3481E-15 16.78E+00 4 Sr 87m 1.0671E-15 14.81E-02 Y 90m 3.4726E-15 10.89E+00 5 Rb 86 8.9150E-16 12.37E-02 Rb 86m 2.8606E-15 89.73E-01 6 Y 90 3.8676E-17 53.68E-04 Y 88 1.2084E-15 37.90E-01 7 Sr 89 7.9504E-19 11.03E-05 Sr 87m 2.2134E-16 69.43E-02 8 0.0000E+00 00.00E+00 H 3 7.2341E-22 22.69E-07 9 0.0000E+00 00.00E+00 C 14 1.5896E-22 49.86E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 3.67133E+03 +/- 6.21E+02 Bq. Error is 1.69E+01 % of the total. Total Heat Production is 7.52389E-13 +/- 6.84E-14 kW. Error is 9.09E+00 % of the total. Total Gamma Dose Rate is 1.22216E-03 +/- 9.64E-05 Sv/hr. Error is 7.89E+00 % of the total. Total Ingestion Dose is 2.17480E-06 +/- 1.87E-07 Sv. Error is 8.61E+00 % of the total. Total Inhalation Dose is 5.91957E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 7.20510E-13 +/- 6.65E-14 kW. Error is 9.23E+00 % of the total. Total Beta Heat Prod is 3.18793E-14 +/- 7.73E-15 kW. Error is 2.42E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Rb 86m 1.57760E+05 4.88E+04 1.793E+03 5.54E+02 1.597E-13 4.94E-14 1.935E-04 5.98E-05 5.378E-09 1.66E-09 8.784E-10 2.72E-10 3.093E+01 Y 88 1.58264E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.73257E+06 4.33E+06 4.667E+02 2.61E+02 5.097E-14 2.85E-14 5.019E-05 2.81E-05 7.934E-08 4.44E-08 4.667E-08 2.61E-08 5.596E+01 Rb 86 1.37855E+08 3.49E+07 5.933E+01 1.50E+01 7.129E-15 1.81E-15 1.572E-06 3.98E-07 1.661E-07 4.21E-08 5.518E-08 1.40E-08 2.534E+01 Y 90 2.79346E+07 1.56E+07 8.404E+01 4.69E+01 1.257E-14 7.02E-15 6.844E-13 3.82E-13 2.269E-07 1.27E-07 1.261E-07 7.04E-08 5.581E+01 Sr 89 3.59916E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.03557E+05 2.16E+05 2.076E+01 1.47E+01 1.288E-15 9.15E-16 1.012E-06 7.19E-07 6.227E-10 4.42E-10 4.359E-10 3.09E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 12 * * * COOLING TIME IS 9.9000E+01 SECS OR 1.6500E+00 MINS * * * ELAPSED TIME IS 8.033 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37956E+08 1.968E-14 5.938E+01 6.242E-15 0.00E+00 8.922E-16 1.573E-06 1.663E-07 5.522E-08 1.610E+06 Rb 86m ? 5.15094E+04 7.348E-18 5.853E+02 9.340E-16 0.00E+00 5.120E-14 6.317E-05 1.756E-09 2.868E-10 6.100E+01 Sr 87m 3.01509E+05 4.351E-17 2.062E+01 2.198E-16 0.00E+00 1.060E-15 1.006E-06 6.185E-10 4.329E-10 1.014E+04 Sr 89 3.59911E+08 5.314E-14 5.710E+01 5.348E-15 0.00E+00 7.950E-19 1.303E-09 1.485E-07 4.511E-07 4.369E+06 Y 88 1.58263E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.79724E+07 4.176E-15 8.415E+01 1.255E-14 0.00E+00 3.873E-17 6.853E-13 2.272E-07 1.262E-07 2.304E+05 Y 90m 7.68651E+06 1.148E-15 4.639E+02 3.452E-15 0.00E+00 4.722E-14 4.989E-05 7.887E-08 4.639E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 9 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 6.65195E-08 0.00000E+00 5.05257E-09 1.03676E-07 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.391432E+03 GAMMA BECQUERELS = 1.069788E+03 0 TOTAL ACTIVITY FOR ALL MATERIALS 2.46122E+03 Bq 3.33262E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 2.46122E+03 Bq 3.33262E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.99519E-14 kW TOTAL GAMMA HEAT PRODUCTION 6.14596E-13 kW TOTAL HEAT PRODUCTION 6.44548E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 6.44548E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.17112E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91886E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.17112E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91886E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 4.1774E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3808E+08 2.2929E-16 1.9698E-14 1.2106E-09 7.1762E-15 8.7880E-09 5.2096E-14 0.0000E+00 0.0000E+00 38 Sr 1.9490E+09 3.2363E-15 2.8509E-13 9.3925E-10 5.5679E-15 1.7893E-10 1.0607E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9028E-09 1.7208E-14 9.4709E-08 5.6144E-13 0.0000E+00 0.0000E+00 40 Zr 5.2964E+04 8.7949E-20 7.9070E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.86945E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.83601E+03 Total gammas (per cc per second) 2.24563E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.29529E-02 Gammas per group (per cc per second) 4.30388E+01 ( 0.010- 0.020 MeV) 1.08817E+01 3.63449E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.11579E+01 1.82681E+03 ( 0.300- 0.400 MeV) 6.58401E+00 9.42454E+01 ( 0.400- 0.600 MeV) 5.24026E+02 5.25074E+03 ( 0.600- 0.800 MeV) 1.02150E+00 7.31102E+00 ( 0.800- 1.000 MeV) 1.00458E+03 5.59219E+03 ( 1.000- 1.220 MeV) 5.56836E+00 2.51329E+01 ( 1.220- 1.440 MeV) 2.63371E-01 9.92098E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17138E+03 5.94460E+03 ( 2.000- 2.500 MeV) 2.07900E-06 4.62924E-06 ( 2.500- 3.000 MeV) 1.99891E+01 3.64165E+01 ( 3.000- 4.000 MeV) 2.68260E-01 3.83995E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.09155E-03 Sieverts/hour ( 1.09155E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 2.4612E+03 Total 6.4455E-13 Total 1.0916E-03 Total 2.1711E-06 Total 5.9189E-06 1 Y 88 1.1907E+03 48.38E+00 Y 88 5.1539E-13 79.96E+00 Y 88 9.7591E-04 89.41E+00 Y 88 1.5480E-06 71.30E+00 Y 88 5.2392E-06 88.52E+00 2 Rb 86m 5.8530E+02 23.78E+00 Rb 86m 5.2138E-14 80.89E-01 Rb 86m 6.3168E-05 57.87E-01 Y 90 2.2721E-07 10.47E+00 Sr 89 4.5107E-07 76.21E-01 3 Y 90m 4.6394E+02 18.85E+00 Y 90m 5.0670E-14 78.61E-01 Y 90m 4.9893E-05 45.71E-01 Rb 86 1.6625E-07 76.57E-01 Y 90 1.2623E-07 21.33E-01 4 Y 90 8.4153E+01 34.19E-01 Y 90 1.2586E-14 19.53E-01 Rb 86 1.5733E-06 14.41E-02 Sr 89 1.4845E-07 68.38E-01 Rb 86 5.5219E-08 93.29E-02 5 Rb 86 5.9375E+01 24.12E-01 Rb 86 7.1344E-15 11.07E-01 Sr 87m 1.0055E-06 92.12E-03 Y 90m 7.8870E-08 36.33E-01 Y 90m 4.6394E-08 78.38E-02 6 Sr 89 5.7097E+01 23.20E-01 Sr 89 5.3489E-15 82.99E-02 Sr 89 1.3026E-09 11.93E-05 Rb 86m 1.7559E-09 80.88E-03 Sr 87m 4.3292E-10 73.14E-04 7 Sr 87m 2.0615E+01 83.76E-02 Sr 87m 1.2797E-15 19.85E-02 Y 90 6.8533E-13 62.79E-09 Sr 87m 6.1846E-10 28.49E-03 Rb 86m 2.8680E-10 48.46E-04 8 H 3 7.9111E-04 32.14E-06 H 3 7.2341E-22 11.22E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.30E-07 H 3 2.0569E-13 34.75E-07 9 C 14 2.0054E-05 81.48E-08 C 14 1.5896E-22 24.66E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.57E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 6.1460E-13 Total 2.9952E-14 1 Y 88 5.1418E-13 83.66E+00 Y 90 1.2547E-14 41.89E+00 2 Rb 86m 5.1204E-14 83.31E-01 Rb 86 6.2422E-15 20.84E+00 3 Y 90m 4.7218E-14 76.83E-01 Sr 89 5.3481E-15 17.86E+00 4 Sr 87m 1.0599E-15 17.25E-02 Y 90m 3.4520E-15 11.53E+00 5 Rb 86 8.9215E-16 14.52E-02 Y 88 1.2083E-15 40.34E-01 6 Y 90 3.8729E-17 63.01E-04 Rb 86m 9.3399E-16 31.18E-01 7 Sr 89 7.9503E-19 12.94E-05 Sr 87m 2.1985E-16 73.40E-02 8 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.15E-07 9 0.0000E+00 00.00E+00 C 14 1.5896E-22 53.07E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 2.46122E+03 +/- 3.33E+02 Bq. Error is 1.35E+01 % of the total. Total Heat Production is 6.44548E-13 +/- 4.99E-14 kW. Error is 7.75E+00 % of the total. Total Gamma Dose Rate is 1.09155E-03 +/- 7.80E-05 Sv/hr. Error is 7.14E+00 % of the total. Total Ingestion Dose is 2.17112E-06 +/- 1.87E-07 Sv. Error is 8.62E+00 % of the total. Total Inhalation Dose is 5.91886E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 6.14596E-13 +/- 4.81E-14 kW. Error is 7.83E+00 % of the total. Total Beta Heat Prod is 2.99519E-14 +/- 7.69E-15 kW. Error is 2.57E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Rb 86m 5.15094E+04 1.59E+04 5.853E+02 1.81E+02 5.214E-14 1.61E-14 6.317E-05 1.95E-05 1.756E-09 5.43E-10 2.868E-10 8.87E-11 3.093E+01 Y 88 1.58263E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.68651E+06 4.30E+06 4.639E+02 2.60E+02 5.067E-14 2.84E-14 4.989E-05 2.79E-05 7.887E-08 4.41E-08 4.639E-08 2.60E-08 5.596E+01 Rb 86 1.37956E+08 3.50E+07 5.938E+01 1.50E+01 7.134E-15 1.81E-15 1.573E-06 3.99E-07 1.663E-07 4.21E-08 5.522E-08 1.40E-08 2.534E+01 Y 90 2.79724E+07 1.56E+07 8.415E+01 4.70E+01 1.259E-14 7.02E-15 6.853E-13 3.83E-13 2.272E-07 1.27E-07 1.262E-07 7.05E-08 5.581E+01 Sr 89 3.59911E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.485E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 3.01509E+05 2.14E+05 2.062E+01 1.46E+01 1.280E-15 9.09E-16 1.006E-06 7.14E-07 6.185E-10 4.39E-10 4.329E-10 3.07E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 13 * * * COOLING TIME IS 1.2700E+02 SECS OR 2.1167E+00 MINS * * * ELAPSED TIME IS 10.150 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37987E+08 1.969E-14 5.939E+01 6.244E-15 0.00E+00 8.924E-16 1.574E-06 1.663E-07 5.523E-08 1.610E+06 Rb 86m ? 1.23394E+04 1.760E-18 1.402E+02 2.237E-16 0.00E+00 1.227E-14 1.513E-05 4.206E-10 6.870E-11 6.100E+01 Sr 87m 2.98902E+05 4.314E-17 2.044E+01 2.179E-16 0.00E+00 1.051E-15 9.968E-07 6.131E-10 4.292E-10 1.014E+04 Sr 89 3.59903E+08 5.313E-14 5.710E+01 5.348E-15 0.00E+00 7.950E-19 1.303E-09 1.484E-07 4.511E-07 4.369E+06 Y 88 1.58261E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.80204E+07 4.183E-15 8.430E+01 1.257E-14 0.00E+00 3.880E-17 6.865E-13 2.276E-07 1.264E-07 2.304E+05 Y 90m 7.62781E+06 1.139E-15 4.604E+02 3.426E-15 0.00E+00 4.686E-14 4.951E-05 7.827E-08 4.604E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 9 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 5.43933E-08 0.00000E+00 4.93184E-09 9.70444E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.391577E+03 GAMMA BECQUERELS = 6.209766E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 2.01255E+03 Bq 2.72511E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 2.01255E+03 Bq 2.72511E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.92362E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.75284E-13 kW TOTAL HEAT PRODUCTION 6.04520E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 6.04520E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16958E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91845E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16958E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91845E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 4.9308E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3807E+08 2.2927E-16 1.9697E-14 1.0910E-09 6.4674E-15 2.2197E-09 1.3159E-14 0.0000E+00 0.0000E+00 38 Sr 1.9491E+09 3.2366E-15 2.8511E-13 9.3891E-10 5.5659E-15 1.7738E-10 1.0515E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9020E-09 1.7203E-14 9.4647E-08 5.6107E-13 0.0000E+00 0.0000E+00 40 Zr 6.3662E+04 1.0571E-19 9.5041E-18 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.82478E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.59064E+03 Total gammas (per cc per second) 1.99687E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.23916E-02 Gammas per group (per cc per second) 4.24763E+01 ( 0.010- 0.020 MeV) 1.08155E+01 3.61237E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 9.04619E+01 1.81286E+03 ( 0.300- 0.400 MeV) 6.52708E+00 9.34306E+01 ( 0.400- 0.600 MeV) 2.79517E+02 2.80076E+03 ( 0.600- 0.800 MeV) 1.01370E+00 7.25519E+00 ( 0.800- 1.000 MeV) 1.00458E+03 5.59213E+03 ( 1.000- 1.220 MeV) 5.56964E+00 2.51386E+01 ( 1.220- 1.440 MeV) 2.63369E-01 9.92089E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17136E+03 5.94454E+03 ( 2.000- 2.500 MeV) 2.08257E-06 4.63718E-06 ( 2.500- 3.000 MeV) 1.99889E+01 3.64161E+01 ( 3.000- 4.000 MeV) 2.68257E-01 3.83991E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.04312E-03 Sieverts/hour ( 1.04312E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 2.0126E+03 Total 6.0452E-13 Total 1.0431E-03 Total 2.1696E-06 Total 5.9185E-06 1 Y 88 1.1907E+03 59.16E+00 Y 88 5.1539E-13 85.26E+00 Y 88 9.7590E-04 93.56E+00 Y 88 1.5479E-06 71.35E+00 Y 88 5.2392E-06 88.52E+00 2 Y 90m 4.6040E+02 22.88E+00 Y 90m 5.0283E-14 83.18E-01 Y 90m 4.9512E-05 47.47E-01 Y 90 2.2760E-07 10.49E+00 Sr 89 4.5106E-07 76.21E-01 3 Rb 86m 1.4021E+02 69.67E-01 Y 90 1.2608E-14 20.86E-01 Rb 86m 1.5132E-05 14.51E-01 Rb 86 1.6629E-07 76.65E-01 Y 90 1.2645E-07 21.36E-01 4 Y 90 8.4298E+01 41.89E-01 Rb 86m 1.2490E-14 20.66E-01 Rb 86 1.5736E-06 15.09E-02 Sr 89 1.4845E-07 68.42E-01 Rb 86 5.5232E-08 93.32E-02 5 Rb 86 5.9389E+01 29.51E-01 Rb 86 7.1360E-15 11.80E-01 Sr 87m 9.9684E-07 95.56E-03 Y 90m 7.8267E-08 36.07E-01 Y 90m 4.6040E-08 77.79E-02 6 Sr 89 5.7096E+01 28.37E-01 Sr 89 5.3487E-15 88.48E-02 Sr 89 1.3026E-09 12.49E-05 Sr 87m 6.1311E-10 28.26E-03 Sr 87m 4.2918E-10 72.52E-04 7 Sr 87m 2.0437E+01 10.15E-01 Sr 87m 1.2687E-15 20.99E-02 Y 90 6.8651E-13 65.81E-09 Rb 86m 4.2064E-10 19.39E-03 Rb 86m 6.8705E-11 11.61E-04 8 H 3 7.9111E-04 39.31E-06 H 3 7.2341E-22 11.97E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.31E-07 H 3 2.0569E-13 34.75E-07 9 C 14 2.0054E-05 99.64E-08 C 14 1.5896E-22 26.30E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.61E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.7528E-13 Total 2.9236E-14 1 Y 88 5.1418E-13 89.38E+00 Y 90 1.2569E-14 42.99E+00 2 Y 90m 4.6857E-14 81.45E-01 Rb 86 6.2437E-15 21.36E+00 3 Rb 86m 1.2266E-14 21.32E-01 Sr 89 5.3480E-15 18.29E+00 4 Sr 87m 1.0507E-15 18.26E-02 Y 90m 3.4256E-15 11.72E+00 5 Rb 86 8.9236E-16 15.51E-02 Y 88 1.2083E-15 41.33E-01 6 Y 90 3.8795E-17 67.44E-04 Rb 86m 2.2374E-16 76.53E-02 7 Sr 89 7.9501E-19 13.82E-05 Sr 87m 2.1795E-16 74.55E-02 8 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.74E-07 9 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.37E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 2.01255E+03 +/- 2.80E+02 Bq. Error is 1.39E+01 % of the total. Total Heat Production is 6.04520E-13 +/- 4.73E-14 kW. Error is 7.82E+00 % of the total. Total Gamma Dose Rate is 1.04312E-03 +/- 7.56E-05 Sv/hr. Error is 7.24E+00 % of the total. Total Ingestion Dose is 2.16958E-06 +/- 1.87E-07 Sv. Error is 8.63E+00 % of the total. Total Inhalation Dose is 5.91845E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.75284E-13 +/- 4.55E-14 kW. Error is 7.90E+00 % of the total. Total Beta Heat Prod is 2.92362E-14 +/- 7.69E-15 kW. Error is 2.63E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Rb 86m 1.23394E+04 3.82E+03 1.402E+02 4.34E+01 1.249E-14 3.86E-15 1.513E-05 4.68E-06 4.206E-10 1.30E-10 6.870E-11 2.12E-11 3.093E+01 Y 88 1.58261E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.62781E+06 4.27E+06 4.604E+02 2.58E+02 5.028E-14 2.81E-14 4.951E-05 2.77E-05 7.827E-08 4.38E-08 4.604E-08 2.58E-08 5.596E+01 Rb 86 1.37987E+08 3.50E+07 5.939E+01 1.50E+01 7.136E-15 1.81E-15 1.574E-06 3.99E-07 1.663E-07 4.21E-08 5.523E-08 1.40E-08 2.534E+01 Y 90 2.80204E+07 1.56E+07 8.430E+01 4.70E+01 1.261E-14 7.04E-15 6.865E-13 3.83E-13 2.276E-07 1.27E-07 1.264E-07 7.06E-08 5.581E+01 Sr 89 3.59903E+08 1.30E+08 5.710E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.484E-07 5.35E-08 4.511E-07 1.63E-07 3.605E+01 Sr 87m 2.98902E+05 2.12E+05 2.044E+01 1.45E+01 1.269E-15 9.01E-16 9.968E-07 7.08E-07 6.131E-10 4.35E-10 4.292E-10 3.05E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 14 * * * COOLING TIME IS 1.2700E+02 SECS OR 2.1167E+00 MINS * * * ELAPSED TIME IS 12.267 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37989E+08 1.969E-14 5.939E+01 6.244E-15 0.00E+00 8.924E-16 1.574E-06 1.663E-07 5.523E-08 1.610E+06 Rb 86m ? 2.98412E+03 4.257E-19 3.391E+01 5.411E-17 0.00E+00 2.966E-15 3.660E-06 1.017E-10 1.662E-11 6.100E+01 Sr 87m 2.96318E+05 4.276E-17 2.026E+01 2.161E-16 0.00E+00 1.042E-15 9.882E-07 6.078E-10 4.255E-10 1.014E+04 Sr 89 3.59896E+08 5.313E-14 5.709E+01 5.348E-15 0.00E+00 7.950E-19 1.303E-09 1.484E-07 4.510E-07 4.369E+06 Y 88 1.58260E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.80679E+07 4.190E-15 8.444E+01 1.259E-14 0.00E+00 3.886E-17 6.877E-13 2.280E-07 1.267E-07 2.304E+05 Y 90m 7.56957E+06 1.130E-15 4.569E+02 3.399E-15 0.00E+00 4.650E-14 4.913E-05 7.767E-08 4.569E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 9 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 5.14240E-08 0.00000E+00 4.90209E-09 9.54129E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.391708E+03 GAMMA BECQUERELS = 5.109799E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.90269E+03 Bq 2.57634E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.90269E+03 Bq 2.57634E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.90598E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.65613E-13 kW TOTAL HEAT PRODUCTION 5.94673E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.94673E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16903E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91820E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16903E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91820E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 5.6842E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3806E+08 2.2926E-16 1.9696E-14 1.0624E-09 6.2979E-15 6.5094E-10 3.8588E-15 0.0000E+00 0.0000E+00 38 Sr 1.9493E+09 3.2368E-15 2.8513E-13 9.3857E-10 5.5639E-15 1.7585E-10 1.0424E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9011E-09 1.7198E-14 9.4586E-08 5.6071E-13 0.0000E+00 0.0000E+00 40 Zr 7.4378E+04 1.2351E-19 1.1104E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.81377E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.53028E+03 Total gammas (per cc per second) 1.93506E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.22254E-02 Gammas per group (per cc per second) 4.23098E+01 ( 0.010- 0.020 MeV) 1.07965E+01 3.60604E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.97711E+01 1.79901E+03 ( 0.300- 0.400 MeV) 6.47065E+00 9.26228E+01 ( 0.400- 0.600 MeV) 2.19956E+02 2.20396E+03 ( 0.600- 0.800 MeV) 1.00596E+00 7.19979E+00 ( 0.800- 1.000 MeV) 1.00457E+03 5.59208E+03 ( 1.000- 1.220 MeV) 5.56971E+00 2.51390E+01 ( 1.220- 1.440 MeV) 2.63366E-01 9.92079E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17134E+03 5.94449E+03 ( 2.000- 2.500 MeV) 2.08610E-06 4.64505E-06 ( 2.500- 3.000 MeV) 1.99887E+01 3.64158E+01 ( 3.000- 4.000 MeV) 2.68255E-01 3.83987E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.03125E-03 Sieverts/hour ( 1.03125E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.9027E+03 Total 5.9467E-13 Total 1.0312E-03 Total 2.1690E-06 Total 5.9182E-06 1 Y 88 1.1907E+03 62.58E+00 Y 88 5.1538E-13 86.67E+00 Y 88 9.7589E-04 94.63E+00 Y 88 1.5479E-06 71.36E+00 Y 88 5.2391E-06 88.53E+00 2 Y 90m 4.5688E+02 24.01E+00 Y 90m 4.9899E-14 83.91E-01 Y 90m 4.9134E-05 47.64E-01 Y 90 2.2799E-07 10.51E+00 Sr 89 4.5105E-07 76.21E-01 3 Y 90 8.4441E+01 44.38E-01 Y 90 1.2629E-14 21.24E-01 Rb 86m 3.6596E-06 35.49E-02 Rb 86 1.6629E-07 76.67E-01 Y 90 1.2666E-07 21.40E-01 4 Rb 86 5.9389E+01 31.21E-01 Rb 86 7.1361E-15 12.00E-01 Rb 86 1.5736E-06 15.26E-02 Sr 89 1.4845E-07 68.44E-01 Rb 86 5.5232E-08 93.33E-02 5 Sr 89 5.7095E+01 30.01E-01 Sr 89 5.3486E-15 89.94E-02 Sr 87m 9.8822E-07 95.83E-03 Y 90m 7.7670E-08 35.81E-01 Y 90m 4.5688E-08 77.20E-02 6 Rb 86m 3.3909E+01 17.82E-01 Rb 86m 3.0205E-15 50.79E-02 Sr 89 1.3026E-09 12.63E-05 Sr 87m 6.0781E-10 28.02E-03 Sr 87m 4.2547E-10 71.89E-04 7 Sr 87m 2.0260E+01 10.65E-01 Sr 87m 1.2577E-15 21.15E-02 Y 90 6.8767E-13 66.68E-09 Rb 86m 1.0173E-10 46.90E-04 Rb 86m 1.6615E-11 28.07E-05 8 H 3 7.9111E-04 41.58E-06 H 3 7.2341E-22 12.16E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.32E-07 H 3 2.0569E-13 34.76E-07 9 C 14 2.0054E-05 10.54E-07 C 14 1.5896E-22 26.73E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.62E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.6561E-13 Total 2.9060E-14 1 Y 88 5.1417E-13 90.91E+00 Y 90 1.2590E-14 43.33E+00 2 Y 90m 4.6499E-14 82.21E-01 Rb 86 6.2438E-15 21.49E+00 3 Rb 86m 2.9664E-15 52.45E-02 Sr 89 5.3478E-15 18.40E+00 4 Sr 87m 1.0416E-15 18.42E-02 Y 90m 3.3994E-15 11.70E+00 5 Rb 86 8.9237E-16 15.78E-02 Y 88 1.2083E-15 41.58E-01 6 Y 90 3.8861E-17 68.71E-04 Sr 87m 2.1606E-16 74.35E-02 7 Sr 89 7.9500E-19 14.06E-05 Rb 86m 5.4109E-17 18.62E-02 8 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.89E-07 9 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.70E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.90269E+03 +/- 2.75E+02 Bq. Error is 1.45E+01 % of the total. Total Heat Production is 5.94673E-13 +/- 4.70E-14 kW. Error is 7.90E+00 % of the total. Total Gamma Dose Rate is 1.03125E-03 +/- 7.53E-05 Sv/hr. Error is 7.31E+00 % of the total. Total Ingestion Dose is 2.16903E-06 +/- 1.87E-07 Sv. Error is 8.64E+00 % of the total. Total Inhalation Dose is 5.91820E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.65613E-13 +/- 4.52E-14 kW. Error is 7.99E+00 % of the total. Total Beta Heat Prod is 2.90598E-14 +/- 7.70E-15 kW. Error is 2.65E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Rb 86m 2.98412E+03 9.23E+02 3.391E+01 1.05E+01 3.021E-15 9.34E-16 3.660E-06 1.13E-06 1.017E-10 3.15E-11 1.662E-11 5.14E-12 3.093E+01 Y 88 1.58260E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.56957E+06 4.24E+06 4.569E+02 2.56E+02 4.990E-14 2.79E-14 4.913E-05 2.75E-05 7.767E-08 4.35E-08 4.569E-08 2.56E-08 5.596E+01 Rb 86 1.37989E+08 3.50E+07 5.939E+01 1.50E+01 7.136E-15 1.81E-15 1.574E-06 3.99E-07 1.663E-07 4.21E-08 5.523E-08 1.40E-08 2.534E+01 Y 90 2.80679E+07 1.57E+07 8.444E+01 4.71E+01 1.263E-14 7.05E-15 6.877E-13 3.84E-13 2.280E-07 1.27E-07 1.267E-07 7.07E-08 5.581E+01 Sr 89 3.59896E+08 1.30E+08 5.709E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.484E-07 5.35E-08 4.510E-07 1.63E-07 3.605E+01 Sr 87m 2.96318E+05 2.10E+05 2.026E+01 1.44E+01 1.258E-15 8.93E-16 9.882E-07 7.02E-07 6.078E-10 4.32E-10 4.255E-10 3.02E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 15 * * * COOLING TIME IS 1.2400E+02 SECS OR 2.0667E+00 MINS * * * ELAPSED TIME IS 14.333 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37984E+08 1.968E-14 5.939E+01 6.244E-15 0.00E+00 8.923E-16 1.574E-06 1.663E-07 5.523E-08 1.610E+06 Sr 87m 2.93816E+05 4.240E-17 2.009E+01 2.142E-16 0.00E+00 1.033E-15 9.799E-07 6.027E-10 4.219E-10 1.014E+04 Sr 89 3.59889E+08 5.313E-14 5.709E+01 5.348E-15 0.00E+00 7.950E-19 1.303E-09 1.484E-07 4.510E-07 4.369E+06 Y 88 1.58258E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.81138E+07 4.197E-15 8.458E+01 1.261E-14 0.00E+00 3.892E-17 6.888E-13 2.284E-07 1.269E-07 2.304E+05 Y 90m 7.51312E+06 1.122E-15 4.535E+02 3.374E-15 0.00E+00 4.615E-14 4.877E-05 7.709E-08 4.535E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 5.04142E-08 0.00000E+00 4.89180E-09 9.48517E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.391831E+03 GAMMA BECQUERELS = 4.734940E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.86532E+03 Bq 2.52575E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.86532E+03 Bq 2.52575E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.89988E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.62286E-13 kW TOTAL HEAT PRODUCTION 5.91285E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.91285E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16870E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91799E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16870E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91799E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 6.4198E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3806E+08 2.2925E-16 1.9695E-14 1.0532E-09 6.2435E-15 1.5053E-10 8.9234E-16 0.0000E+00 0.0000E+00 38 Sr 1.9494E+09 3.2371E-15 2.8515E-13 9.3825E-10 5.5620E-15 1.7436E-10 1.0336E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.9003E-09 1.7193E-14 9.4527E-08 5.6036E-13 0.0000E+00 0.0000E+00 40 Zr 8.4858E+04 1.4091E-19 1.2669E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80996E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.50951E+03 Total gammas (per cc per second) 1.91330E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.21449E-02 Gammas per group (per cc per second) 4.22292E+01 ( 0.010- 0.020 MeV) 1.07878E+01 3.60313E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.91017E+01 1.78560E+03 ( 0.300- 0.400 MeV) 6.41602E+00 9.18408E+01 ( 0.400- 0.600 MeV) 1.99962E+02 2.00362E+03 ( 0.600- 0.800 MeV) 9.98458E-01 7.14611E+00 ( 0.800- 1.000 MeV) 1.00456E+03 5.59203E+03 ( 1.000- 1.220 MeV) 5.56951E+00 2.51380E+01 ( 1.220- 1.440 MeV) 2.63364E-01 9.92070E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17132E+03 5.94443E+03 ( 2.000- 2.500 MeV) 2.08951E-06 4.65265E-06 ( 2.500- 3.000 MeV) 1.99885E+01 3.64154E+01 ( 3.000- 4.000 MeV) 2.68252E-01 3.83984E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02720E-03 Sieverts/hour ( 1.02720E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8653E+03 Total 5.9128E-13 Total 1.0272E-03 Total 2.1687E-06 Total 5.9180E-06 1 Y 88 1.1907E+03 63.83E+00 Y 88 5.1538E-13 87.16E+00 Y 88 9.7588E-04 95.00E+00 Y 88 1.5479E-06 71.38E+00 Y 88 5.2391E-06 88.53E+00 2 Y 90m 4.5347E+02 24.31E+00 Y 90m 4.9527E-14 83.76E-01 Y 90m 4.8767E-05 47.48E-01 Y 90 2.2836E-07 10.53E+00 Sr 89 4.5104E-07 76.21E-01 3 Y 90 8.4579E+01 45.34E-01 Y 90 1.2650E-14 21.39E-01 Rb 86 1.5736E-06 15.32E-02 Rb 86 1.6628E-07 76.67E-01 Y 90 1.2687E-07 21.44E-01 4 Rb 86 5.9387E+01 31.84E-01 Rb 86 7.1359E-15 12.07E-01 Sr 87m 9.7987E-07 95.39E-03 Sr 89 1.4844E-07 68.45E-01 Rb 86 5.5230E-08 93.33E-02 5 Sr 89 5.7094E+01 30.61E-01 Sr 89 5.3485E-15 90.46E-02 Sr 89 1.3026E-09 12.68E-05 Y 90m 7.7091E-08 35.55E-01 Y 90m 4.5347E-08 76.63E-02 6 Sr 87m 2.0089E+01 10.77E-01 Sr 87m 1.2471E-15 21.09E-02 Y 90 6.8880E-13 67.06E-09 Sr 87m 6.0268E-10 27.79E-03 Sr 87m 4.2188E-10 71.29E-04 7 H 3 7.9111E-04 42.41E-06 H 3 7.2341E-22 12.23E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.32E-07 H 3 2.0569E-13 34.76E-07 8 C 14 2.0054E-05 10.75E-07 C 14 1.5896E-22 26.88E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.63E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.6229E-13 Total 2.8999E-14 1 Y 88 5.1417E-13 91.44E+00 Y 90 1.2611E-14 43.49E+00 2 Y 90m 4.6153E-14 82.08E-01 Rb 86 6.2435E-15 21.53E+00 3 Sr 87m 1.0328E-15 18.37E-02 Sr 89 5.3477E-15 18.44E+00 4 Rb 86 8.9234E-16 15.87E-02 Y 90m 3.3741E-15 11.64E+00 5 Y 90 3.8925E-17 69.23E-04 Y 88 1.2083E-15 41.67E-01 6 Sr 89 7.9498E-19 14.14E-05 Sr 87m 2.1424E-16 73.88E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.95E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.82E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.86532E+03 +/- 2.73E+02 Bq. Error is 1.47E+01 % of the total. Total Heat Production is 5.91285E-13 +/- 4.69E-14 kW. Error is 7.93E+00 % of the total. Total Gamma Dose Rate is 1.02720E-03 +/- 7.53E-05 Sv/hr. Error is 7.33E+00 % of the total. Total Ingestion Dose is 2.16870E-06 +/- 1.87E-07 Sv. Error is 8.64E+00 % of the total. Total Inhalation Dose is 5.91799E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.62286E-13 +/- 4.51E-14 kW. Error is 8.02E+00 % of the total. Total Beta Heat Prod is 2.89988E-14 +/- 7.70E-15 kW. Error is 2.66E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58258E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.77E-07 7.186E+00 Y 90m 7.51312E+06 4.20E+06 4.535E+02 2.54E+02 4.953E-14 2.77E-14 4.877E-05 2.73E-05 7.709E-08 4.31E-08 4.535E-08 2.54E-08 5.596E+01 Rb 86 1.37984E+08 3.50E+07 5.939E+01 1.50E+01 7.136E-15 1.81E-15 1.574E-06 3.99E-07 1.663E-07 4.21E-08 5.523E-08 1.40E-08 2.534E+01 Y 90 2.81138E+07 1.57E+07 8.458E+01 4.72E+01 1.265E-14 7.06E-15 6.888E-13 3.84E-13 2.284E-07 1.27E-07 1.269E-07 7.08E-08 5.581E+01 Sr 89 3.59889E+08 1.30E+08 5.709E+01 2.06E+01 5.349E-15 1.93E-15 1.303E-09 4.70E-10 1.484E-07 5.35E-08 4.510E-07 1.63E-07 3.605E+01 Sr 87m 2.93816E+05 2.09E+05 2.009E+01 1.43E+01 1.247E-15 8.86E-16 9.799E-07 6.96E-07 6.027E-10 4.28E-10 4.219E-10 3.00E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 16 * * * COOLING TIME IS 1.8800E+02 SECS OR 3.1333E+00 MINS * * * ELAPSED TIME IS 17.467 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44099E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37974E+08 1.968E-14 5.938E+01 6.243E-15 0.00E+00 8.923E-16 1.573E-06 1.663E-07 5.523E-08 1.610E+06 Sr 87m 2.90064E+05 4.186E-17 1.983E+01 2.115E-16 0.00E+00 1.020E-15 9.674E-07 5.950E-10 4.165E-10 1.014E+04 Sr 89 3.59878E+08 5.313E-14 5.709E+01 5.348E-15 0.00E+00 7.950E-19 1.303E-09 1.484E-07 4.510E-07 4.369E+06 Y 88 1.58256E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.81827E+07 4.208E-15 8.479E+01 1.264E-14 0.00E+00 3.902E-17 6.905E-13 2.289E-07 1.272E-07 2.304E+05 Y 90m 7.42835E+06 1.109E-15 4.484E+02 3.336E-15 0.00E+00 4.563E-14 4.822E-05 7.622E-08 4.484E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 5.02739E-08 0.00000E+00 4.89001E-09 9.47604E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.392014E+03 GAMMA BECQUERELS = 4.681217E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.86014E+03 Bq 2.51872E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.86013E+03 Bq 2.51872E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.89883E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.61745E-13 kW TOTAL HEAT PRODUCTION 5.90733E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.90733E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16834E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91769E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16834E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91769E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 7.5350E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3805E+08 2.2923E-16 1.9693E-14 1.0531E-09 6.2430E-15 1.5052E-10 8.9227E-16 0.0000E+00 0.0000E+00 38 Sr 1.9496E+09 3.2374E-15 2.8519E-13 9.3776E-10 5.5591E-15 1.7214E-10 1.0204E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8991E-09 1.7186E-14 9.4438E-08 5.5983E-13 0.0000E+00 0.0000E+00 40 Zr 1.0078E+05 1.6735E-19 1.5046E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80930E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.50614E+03 Total gammas (per cc per second) 1.90870E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.20834E-02 Gammas per group (per cc per second) 4.21675E+01 ( 0.010- 0.020 MeV) 1.07818E+01 3.60113E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.80964E+01 1.76545E+03 ( 0.300- 0.400 MeV) 6.33408E+00 9.06678E+01 ( 0.400- 0.600 MeV) 1.97734E+02 1.98129E+03 ( 0.600- 0.800 MeV) 9.87192E-01 7.06548E+00 ( 0.800- 1.000 MeV) 1.00454E+03 5.59195E+03 ( 1.000- 1.220 MeV) 5.56908E+00 2.51361E+01 ( 1.220- 1.440 MeV) 2.63360E-01 9.92056E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17129E+03 5.94435E+03 ( 2.000- 2.500 MeV) 2.09463E-06 4.66405E-06 ( 2.500- 3.000 MeV) 1.99882E+01 3.64149E+01 ( 3.000- 4.000 MeV) 2.68248E-01 3.83978E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02663E-03 Sieverts/hour ( 1.02663E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8601E+03 Total 5.9073E-13 Total 1.0266E-03 Total 2.1683E-06 Total 5.9177E-06 1 Y 88 1.1907E+03 64.01E+00 Y 88 5.1537E-13 87.24E+00 Y 88 9.7587E-04 95.06E+00 Y 88 1.5479E-06 71.39E+00 Y 88 5.2390E-06 88.53E+00 2 Y 90m 4.4836E+02 24.10E+00 Y 90m 4.8968E-14 82.89E-01 Y 90m 4.8217E-05 46.97E-01 Y 90 2.2892E-07 10.56E+00 Sr 89 4.5103E-07 76.22E-01 3 Y 90 8.4786E+01 45.58E-01 Y 90 1.2681E-14 21.47E-01 Rb 86 1.5735E-06 15.33E-02 Rb 86 1.6627E-07 76.68E-01 Y 90 1.2718E-07 21.49E-01 4 Rb 86 5.9383E+01 31.92E-01 Rb 86 7.1353E-15 12.08E-01 Sr 87m 9.6736E-07 94.23E-03 Sr 89 1.4844E-07 68.46E-01 Rb 86 5.5226E-08 93.32E-02 5 Sr 89 5.7092E+01 30.69E-01 Sr 89 5.3484E-15 90.54E-02 Sr 89 1.3025E-09 12.69E-05 Y 90m 7.6221E-08 35.15E-01 Y 90m 4.4836E-08 75.77E-02 6 Sr 87m 1.9833E+01 10.66E-01 Sr 87m 1.2312E-15 20.84E-02 Y 90 6.9049E-13 67.26E-09 Sr 87m 5.9498E-10 27.44E-03 Sr 87m 4.1649E-10 70.38E-04 7 H 3 7.9111E-04 42.53E-06 H 3 7.2341E-22 12.25E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.32E-07 H 3 2.0569E-13 34.76E-07 8 C 14 2.0054E-05 10.78E-07 C 14 1.5896E-22 26.91E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.64E-08 C 14 1.1631E-13 19.65E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.6174E-13 Total 2.8988E-14 1 Y 88 5.1416E-13 91.53E+00 Y 90 1.2642E-14 43.61E+00 2 Y 90m 4.5632E-14 81.23E-01 Rb 86 6.2430E-15 21.54E+00 3 Sr 87m 1.0197E-15 18.15E-02 Sr 89 5.3476E-15 18.45E+00 4 Rb 86 8.9227E-16 15.88E-02 Y 90m 3.3360E-15 11.51E+00 5 Y 90 3.9020E-17 69.46E-04 Y 88 1.2083E-15 41.68E-01 6 Sr 89 7.9496E-19 14.15E-05 Sr 87m 2.1150E-16 72.96E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.96E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.84E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.86014E+03 +/- 2.71E+02 Bq. Error is 1.46E+01 % of the total. Total Heat Production is 5.90733E-13 +/- 4.67E-14 kW. Error is 7.90E+00 % of the total. Total Gamma Dose Rate is 1.02663E-03 +/- 7.51E-05 Sv/hr. Error is 7.32E+00 % of the total. Total Ingestion Dose is 2.16834E-06 +/- 1.88E-07 Sv. Error is 8.65E+00 % of the total. Total Inhalation Dose is 5.91769E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.61745E-13 +/- 4.49E-14 kW. Error is 8.00E+00 % of the total. Total Beta Heat Prod is 2.89883E-14 +/- 7.71E-15 kW. Error is 2.66E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58256E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.76E-07 7.186E+00 Y 90m 7.42835E+06 4.16E+06 4.484E+02 2.51E+02 4.897E-14 2.74E-14 4.822E-05 2.70E-05 7.622E-08 4.27E-08 4.484E-08 2.51E-08 5.596E+01 Rb 86 1.37974E+08 3.50E+07 5.938E+01 1.50E+01 7.135E-15 1.81E-15 1.573E-06 3.99E-07 1.663E-07 4.21E-08 5.523E-08 1.40E-08 2.534E+01 Y 90 2.81827E+07 1.57E+07 8.479E+01 4.73E+01 1.268E-14 7.08E-15 6.905E-13 3.85E-13 2.289E-07 1.28E-07 1.272E-07 7.10E-08 5.581E+01 Sr 89 3.59878E+08 1.30E+08 5.709E+01 2.06E+01 5.348E-15 1.93E-15 1.303E-09 4.70E-10 1.484E-07 5.35E-08 4.510E-07 1.63E-07 3.605E+01 Sr 87m 2.90064E+05 2.06E+05 1.983E+01 1.41E+01 1.231E-15 8.74E-16 9.674E-07 6.87E-07 5.950E-10 4.22E-10 4.165E-10 2.96E-10 7.101E+01 H 3 4.44099E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 17 * * * COOLING TIME IS 2.4500E+02 SECS OR 4.0833E+00 MINS * * * ELAPSED TIME IS 21.550 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44098E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37959E+08 1.968E-14 5.938E+01 6.242E-15 0.00E+00 8.922E-16 1.573E-06 1.663E-07 5.522E-08 1.610E+06 Sr 87m 2.85245E+05 4.117E-17 1.950E+01 2.080E-16 0.00E+00 1.003E-15 9.513E-07 5.851E-10 4.096E-10 1.014E+04 Sr 89 3.59864E+08 5.313E-14 5.709E+01 5.347E-15 0.00E+00 7.949E-19 1.302E-09 1.484E-07 4.510E-07 4.369E+06 Y 88 1.58253E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.142E-13 9.759E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.82709E+07 4.221E-15 8.505E+01 1.268E-14 0.00E+00 3.914E-17 6.926E-13 2.296E-07 1.276E-07 2.304E+05 Y 90m 7.31931E+06 1.093E-15 4.418E+02 3.287E-15 0.00E+00 4.496E-14 4.751E-05 7.510E-08 4.418E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 5.00935E-08 0.00000E+00 4.88769E-09 9.46430E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.392248E+03 GAMMA BECQUERELS = 4.612120E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.85346E+03 Bq 2.50968E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.85346E+03 Bq 2.50968E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.89745E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.61049E-13 kW TOTAL HEAT PRODUCTION 5.90023E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.90023E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16787E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91730E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16787E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91730E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 8.9884E-17 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3803E+08 2.2921E-16 1.9691E-14 1.0530E-09 6.2424E-15 1.5050E-10 8.9218E-16 0.0000E+00 0.0000E+00 38 Sr 1.9499E+09 3.2379E-15 2.8523E-13 9.3713E-10 5.5554E-15 1.6928E-10 1.0035E-15 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8975E-09 1.7177E-14 9.4323E-08 5.5915E-13 0.0000E+00 0.0000E+00 40 Zr 1.2159E+05 2.0190E-19 1.8152E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80844E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.50179E+03 Total gammas (per cc per second) 1.90279E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.20042E-02 Gammas per group (per cc per second) 4.20882E+01 ( 0.010- 0.020 MeV) 1.07741E+01 3.59857E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.68032E+01 1.73954E+03 ( 0.300- 0.400 MeV) 6.22886E+00 8.91616E+01 ( 0.400- 0.600 MeV) 1.94868E+02 1.95258E+03 ( 0.600- 0.800 MeV) 9.72702E-01 6.96176E+00 ( 0.800- 1.000 MeV) 1.00452E+03 5.59185E+03 ( 1.000- 1.220 MeV) 5.56850E+00 2.51335E+01 ( 1.220- 1.440 MeV) 2.63355E-01 9.92038E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17125E+03 5.94424E+03 ( 2.000- 2.500 MeV) 2.10119E-06 4.67865E-06 ( 2.500- 3.000 MeV) 1.99879E+01 3.64142E+01 ( 3.000- 4.000 MeV) 2.68243E-01 3.83971E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02589E-03 Sieverts/hour ( 1.02589E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8535E+03 Total 5.9002E-13 Total 1.0259E-03 Total 2.1679E-06 Total 5.9173E-06 1 Y 88 1.1907E+03 64.24E+00 Y 88 5.1536E-13 87.35E+00 Y 88 9.7585E-04 95.12E+00 Y 88 1.5479E-06 71.40E+00 Y 88 5.2389E-06 88.54E+00 2 Y 90m 4.4178E+02 23.84E+00 Y 90m 4.8249E-14 81.78E-01 Y 90m 4.7509E-05 46.31E-01 Y 90 2.2964E-07 10.59E+00 Sr 89 4.5101E-07 76.22E-01 3 Y 90 8.5052E+01 45.89E-01 Y 90 1.2721E-14 21.56E-01 Rb 86 1.5733E-06 15.34E-02 Rb 86 1.6625E-07 76.69E-01 Y 90 1.2758E-07 21.56E-01 4 Rb 86 5.9377E+01 32.04E-01 Rb 86 7.1346E-15 12.09E-01 Sr 87m 9.5129E-07 92.73E-03 Sr 89 1.4843E-07 68.47E-01 Rb 86 5.5220E-08 93.32E-02 5 Sr 89 5.7090E+01 30.80E-01 Sr 89 5.3482E-15 90.64E-02 Sr 89 1.3025E-09 12.70E-05 Y 90m 7.5102E-08 34.64E-01 Y 90m 4.4178E-08 74.66E-02 6 Sr 87m 1.9503E+01 10.52E-01 Sr 87m 1.2107E-15 20.52E-02 Y 90 6.9265E-13 67.52E-09 Sr 87m 5.8510E-10 26.99E-03 Sr 87m 4.0957E-10 69.22E-04 7 H 3 7.9111E-04 42.68E-06 H 3 7.2341E-22 12.26E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.33E-07 H 3 2.0569E-13 34.76E-07 8 C 14 2.0054E-05 10.82E-07 C 14 1.5896E-22 26.94E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.65E-08 C 14 1.1631E-13 19.66E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.6105E-13 Total 2.8974E-14 1 Y 88 5.1415E-13 91.64E+00 Y 90 1.2681E-14 43.77E+00 2 Y 90m 4.4962E-14 80.14E-01 Rb 86 6.2424E-15 21.54E+00 3 Sr 87m 1.0027E-15 17.87E-02 Sr 89 5.3474E-15 18.46E+00 4 Rb 86 8.9218E-16 15.90E-02 Y 90m 3.2871E-15 11.34E+00 5 Y 90 3.9142E-17 69.77E-04 Y 88 1.2083E-15 41.70E-01 6 Sr 89 7.9493E-19 14.17E-05 Sr 87m 2.0799E-16 71.78E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.97E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.86E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.85346E+03 +/- 2.67E+02 Bq. Error is 1.44E+01 % of the total. Total Heat Production is 5.90023E-13 +/- 4.65E-14 kW. Error is 7.87E+00 % of the total. Total Gamma Dose Rate is 1.02589E-03 +/- 7.50E-05 Sv/hr. Error is 7.31E+00 % of the total. Total Ingestion Dose is 2.16787E-06 +/- 1.88E-07 Sv. Error is 8.66E+00 % of the total. Total Inhalation Dose is 5.91730E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.61049E-13 +/- 4.47E-14 kW. Error is 7.97E+00 % of the total. Total Beta Heat Prod is 2.89745E-14 +/- 7.73E-15 kW. Error is 2.67E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58253E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.759E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.76E-07 7.186E+00 Y 90m 7.31931E+06 4.10E+06 4.418E+02 2.47E+02 4.825E-14 2.70E-14 4.751E-05 2.66E-05 7.510E-08 4.20E-08 4.418E-08 2.47E-08 5.596E+01 Rb 86 1.37959E+08 3.50E+07 5.938E+01 1.50E+01 7.135E-15 1.81E-15 1.573E-06 3.99E-07 1.663E-07 4.21E-08 5.522E-08 1.40E-08 2.534E+01 Y 90 2.82709E+07 1.58E+07 8.505E+01 4.75E+01 1.272E-14 7.10E-15 6.926E-13 3.87E-13 2.296E-07 1.28E-07 1.276E-07 7.12E-08 5.581E+01 Sr 89 3.59864E+08 1.30E+08 5.709E+01 2.06E+01 5.348E-15 1.93E-15 1.302E-09 4.70E-10 1.484E-07 5.35E-08 4.510E-07 1.63E-07 3.605E+01 Sr 87m 2.85245E+05 2.03E+05 1.950E+01 1.38E+01 1.211E-15 8.60E-16 9.513E-07 6.75E-07 5.851E-10 4.15E-10 4.096E-10 2.91E-10 7.101E+01 H 3 4.44098E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 18 * * * COOLING TIME IS 2.4700E+02 SECS OR 4.1167E+00 MINS * * * ELAPSED TIME IS 25.667 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44098E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37944E+08 1.968E-14 5.937E+01 6.242E-15 0.00E+00 8.921E-16 1.573E-06 1.662E-07 5.521E-08 1.610E+06 Sr 87m 2.80468E+05 4.048E-17 1.918E+01 2.045E-16 0.00E+00 9.859E-16 9.354E-07 5.753E-10 4.027E-10 1.014E+04 Sr 89 3.59850E+08 5.313E-14 5.709E+01 5.347E-15 0.00E+00 7.949E-19 1.302E-09 1.484E-07 4.510E-07 4.369E+06 Y 88 1.58250E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.141E-13 9.758E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.83582E+07 4.234E-15 8.531E+01 1.272E-14 0.00E+00 3.926E-17 6.948E-13 2.303E-07 1.280E-07 2.304E+05 Y 90m 7.21100E+06 1.077E-15 4.352E+02 3.238E-15 0.00E+00 4.430E-14 4.681E-05 7.399E-08 4.352E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 4.99143E-08 0.00000E+00 4.88535E-09 9.45263E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.392479E+03 GAMMA BECQUERELS = 4.543492E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.84683E+03 Bq 2.50070E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.84683E+03 Bq 2.50070E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.89606E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.60357E-13 kW TOTAL HEAT PRODUCTION 5.89318E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.89318E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16741E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91692E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16741E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91692E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.0454E-16 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3802E+08 2.2918E-16 1.9689E-14 1.0529E-09 6.2417E-15 1.5048E-10 8.9208E-16 0.0000E+00 0.0000E+00 38 Sr 1.9502E+09 3.2384E-15 2.8527E-13 9.3651E-10 5.5517E-15 1.6645E-10 9.8672E-16 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8959E-09 1.7167E-14 9.4209E-08 5.5848E-13 0.0000E+00 0.0000E+00 40 Zr 1.4263E+05 2.3684E-19 2.1293E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80758E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.49747E+03 Total gammas (per cc per second) 1.89692E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.19256E-02 Gammas per group (per cc per second) 4.20095E+01 ( 0.010- 0.020 MeV) 1.07665E+01 3.59601E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.55187E+01 1.71380E+03 ( 0.300- 0.400 MeV) 6.12454E+00 8.76685E+01 ( 0.400- 0.600 MeV) 1.92021E+02 1.92405E+03 ( 0.600- 0.800 MeV) 9.58308E-01 6.85875E+00 ( 0.800- 1.000 MeV) 1.00450E+03 5.59174E+03 ( 1.000- 1.220 MeV) 5.56791E+00 2.51308E+01 ( 1.220- 1.440 MeV) 2.63350E-01 9.92019E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17121E+03 5.94413E+03 ( 2.000- 2.500 MeV) 2.10768E-06 4.69309E-06 ( 2.500- 3.000 MeV) 1.99875E+01 3.64136E+01 ( 3.000- 4.000 MeV) 2.68238E-01 3.83964E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02515E-03 Sieverts/hour ( 1.02515E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8468E+03 Total 5.8932E-13 Total 1.0251E-03 Total 2.1674E-06 Total 5.9169E-06 1 Y 88 1.1906E+03 64.47E+00 Y 88 5.1535E-13 87.45E+00 Y 88 9.7583E-04 95.19E+00 Y 88 1.5478E-06 71.41E+00 Y 88 5.2388E-06 88.54E+00 2 Y 90m 4.3524E+02 23.57E+00 Y 90m 4.7535E-14 80.66E-01 Y 90m 4.6806E-05 45.66E-01 Y 90 2.3035E-07 10.63E+00 Sr 89 4.5099E-07 76.22E-01 3 Y 90 8.5314E+01 46.20E-01 Y 90 1.2760E-14 21.65E-01 Rb 86 1.5731E-06 15.35E-02 Rb 86 1.6624E-07 76.70E-01 Y 90 1.2797E-07 21.63E-01 4 Rb 86 5.9370E+01 32.15E-01 Rb 86 7.1338E-15 12.11E-01 Sr 87m 9.3536E-07 91.24E-03 Sr 89 1.4843E-07 68.48E-01 Rb 86 5.5214E-08 93.32E-02 5 Sr 89 5.7087E+01 30.91E-01 Sr 89 5.3480E-15 90.75E-02 Sr 89 1.3024E-09 12.70E-05 Y 90m 7.3991E-08 34.14E-01 Y 90m 4.3524E-08 73.56E-02 6 Sr 87m 1.9177E+01 10.38E-01 Sr 87m 1.1904E-15 20.20E-02 Y 90 6.9478E-13 67.77E-09 Sr 87m 5.7530E-10 26.54E-03 Sr 87m 4.0271E-10 68.06E-04 7 H 3 7.9111E-04 42.84E-06 H 3 7.2341E-22 12.28E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.33E-07 H 3 2.0569E-13 34.76E-07 8 C 14 2.0054E-05 10.86E-07 C 14 1.5896E-22 26.97E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.66E-08 C 14 1.1631E-13 19.66E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.6036E-13 Total 2.8961E-14 1 Y 88 5.1414E-13 91.75E+00 Y 90 1.2721E-14 43.92E+00 2 Y 90m 4.4297E-14 79.05E-01 Rb 86 6.2417E-15 21.55E+00 3 Sr 87m 9.8592E-16 17.59E-02 Sr 89 5.3472E-15 18.46E+00 4 Rb 86 8.9208E-16 15.92E-02 Y 90m 3.2384E-15 11.18E+00 5 Y 90 3.9263E-17 70.07E-04 Y 88 1.2083E-15 41.72E-01 6 Sr 89 7.9490E-19 14.19E-05 Sr 87m 2.0451E-16 70.61E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.98E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.89E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.84683E+03 +/- 2.64E+02 Bq. Error is 1.43E+01 % of the total. Total Heat Production is 5.89318E-13 +/- 4.62E-14 kW. Error is 7.85E+00 % of the total. Total Gamma Dose Rate is 1.02515E-03 +/- 7.49E-05 Sv/hr. Error is 7.30E+00 % of the total. Total Ingestion Dose is 2.16741E-06 +/- 1.88E-07 Sv. Error is 8.66E+00 % of the total. Total Inhalation Dose is 5.91692E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.60357E-13 +/- 4.45E-14 kW. Error is 7.94E+00 % of the total. Total Beta Heat Prod is 2.89606E-14 +/- 7.74E-15 kW. Error is 2.67E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58250E+10 1.14E+09 1.191E+03 8.56E+01 5.154E-13 3.70E-14 9.758E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.76E-07 7.186E+00 Y 90m 7.21100E+06 4.04E+06 4.352E+02 2.44E+02 4.754E-14 2.66E-14 4.681E-05 2.62E-05 7.399E-08 4.14E-08 4.352E-08 2.44E-08 5.596E+01 Rb 86 1.37944E+08 3.50E+07 5.937E+01 1.50E+01 7.134E-15 1.81E-15 1.573E-06 3.99E-07 1.662E-07 4.21E-08 5.521E-08 1.40E-08 2.534E+01 Y 90 2.83582E+07 1.58E+07 8.531E+01 4.76E+01 1.276E-14 7.12E-15 6.948E-13 3.88E-13 2.303E-07 1.29E-07 1.280E-07 7.14E-08 5.581E+01 Sr 89 3.59850E+08 1.30E+08 5.709E+01 2.06E+01 5.348E-15 1.93E-15 1.302E-09 4.70E-10 1.484E-07 5.35E-08 4.510E-07 1.63E-07 3.605E+01 Sr 87m 2.80468E+05 1.99E+05 1.918E+01 1.36E+01 1.190E-15 8.45E-16 9.354E-07 6.64E-07 5.753E-10 4.09E-10 4.027E-10 2.86E-10 7.101E+01 H 3 4.44098E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 19 * * * COOLING TIME IS 2.4700E+02 SECS OR 4.1167E+00 MINS * * * ELAPSED TIME IS 29.783 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44098E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37930E+08 1.968E-14 5.936E+01 6.241E-15 0.00E+00 8.920E-16 1.573E-06 1.662E-07 5.521E-08 1.610E+06 Sr 87m 2.75771E+05 3.980E-17 1.886E+01 2.011E-16 0.00E+00 9.694E-16 9.197E-07 5.657E-10 3.960E-10 1.014E+04 Sr 89 3.59836E+08 5.312E-14 5.709E+01 5.347E-15 0.00E+00 7.949E-19 1.302E-09 1.484E-07 4.510E-07 4.369E+06 Y 88 1.58247E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.141E-13 9.758E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.84438E+07 4.246E-15 8.557E+01 1.276E-14 0.00E+00 3.938E-17 6.969E-13 2.310E-07 1.284E-07 2.304E+05 Y 90m 7.10430E+06 1.061E-15 4.288E+02 3.190E-15 0.00E+00 4.364E-14 4.611E-05 7.290E-08 4.288E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 4.97376E-08 0.00000E+00 4.88301E-09 9.44113E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.392705E+03 GAMMA BECQUERELS = 4.475885E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.84029E+03 Bq 2.49186E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.84029E+03 Bq 2.49186E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.89467E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.59675E-13 kW TOTAL HEAT PRODUCTION 5.88622E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.88622E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16695E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91653E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16695E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91653E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.1919E-16 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3800E+08 2.2916E-16 1.9687E-14 1.0528E-09 6.2411E-15 1.5047E-10 8.9199E-16 0.0000E+00 0.0000E+00 38 Sr 1.9505E+09 3.2389E-15 2.8532E-13 9.3589E-10 5.5480E-15 1.6366E-10 9.7021E-16 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8943E-09 1.7158E-14 9.4097E-08 5.5781E-13 0.0000E+00 0.0000E+00 40 Zr 1.6374E+05 2.7189E-19 2.4444E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80671E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.49322E+03 Total gammas (per cc per second) 1.89113E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.18482E-02 Gammas per group (per cc per second) 4.19318E+01 ( 0.010- 0.020 MeV) 1.07590E+01 3.59350E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.42532E+01 1.68843E+03 ( 0.300- 0.400 MeV) 6.02198E+00 8.62003E+01 ( 0.400- 0.600 MeV) 1.89216E+02 1.89595E+03 ( 0.600- 0.800 MeV) 9.44127E-01 6.75725E+00 ( 0.800- 1.000 MeV) 1.00449E+03 5.59164E+03 ( 1.000- 1.220 MeV) 5.56731E+00 2.51282E+01 ( 1.220- 1.440 MeV) 2.63345E-01 9.92001E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17117E+03 5.94402E+03 ( 2.000- 2.500 MeV) 2.11404E-06 4.70726E-06 ( 2.500- 3.000 MeV) 1.99871E+01 3.64129E+01 ( 3.000- 4.000 MeV) 2.68233E-01 3.83957E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02442E-03 Sieverts/hour ( 1.02442E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8403E+03 Total 5.8862E-13 Total 1.0244E-03 Total 2.1669E-06 Total 5.9165E-06 1 Y 88 1.1906E+03 64.70E+00 Y 88 5.1534E-13 87.55E+00 Y 88 9.7581E-04 95.26E+00 Y 88 1.5478E-06 71.43E+00 Y 88 5.2387E-06 88.54E+00 2 Y 90m 4.2880E+02 23.30E+00 Y 90m 4.6832E-14 79.56E-01 Y 90m 4.6114E-05 45.01E-01 Y 90 2.3104E-07 10.66E+00 Sr 89 4.5097E-07 76.22E-01 3 Y 90 8.5572E+01 46.50E-01 Y 90 1.2798E-14 21.74E-01 Rb 86 1.5730E-06 15.35E-02 Rb 86 1.6622E-07 76.71E-01 Y 90 1.2836E-07 21.69E-01 4 Rb 86 5.9364E+01 32.26E-01 Rb 86 7.1330E-15 12.12E-01 Sr 87m 9.1969E-07 89.78E-03 Sr 89 1.4842E-07 68.49E-01 Rb 86 5.5208E-08 93.31E-02 5 Sr 89 5.7085E+01 31.02E-01 Sr 89 5.3477E-15 90.85E-02 Sr 89 1.3024E-09 12.71E-05 Y 90m 7.2896E-08 33.64E-01 Y 90m 4.2880E-08 72.47E-02 6 Sr 87m 1.8856E+01 10.25E-01 Sr 87m 1.1705E-15 19.89E-02 Y 90 6.9688E-13 68.03E-09 Sr 87m 5.6567E-10 26.10E-03 Sr 87m 3.9597E-10 66.93E-04 7 H 3 7.9111E-04 42.99E-06 H 3 7.2341E-22 12.29E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.33E-07 H 3 2.0569E-13 34.77E-07 8 C 14 2.0054E-05 10.90E-07 C 14 1.5896E-22 27.01E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.68E-08 C 14 1.1631E-13 19.66E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.5968E-13 Total 2.8947E-14 1 Y 88 5.1413E-13 91.86E+00 Y 90 1.2759E-14 44.08E+00 2 Y 90m 4.3641E-14 77.98E-01 Rb 86 6.2411E-15 21.56E+00 3 Sr 87m 9.6941E-16 17.32E-02 Sr 89 5.3470E-15 18.47E+00 4 Rb 86 8.9199E-16 15.94E-02 Y 90m 3.1905E-15 11.02E+00 5 Y 90 3.9381E-17 70.36E-04 Y 88 1.2082E-15 41.74E-01 6 Sr 89 7.9487E-19 14.20E-05 Sr 87m 2.0108E-16 69.47E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 24.99E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.92E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.84029E+03 +/- 2.61E+02 Bq. Error is 1.42E+01 % of the total. Total Heat Production is 5.88622E-13 +/- 4.60E-14 kW. Error is 7.82E+00 % of the total. Total Gamma Dose Rate is 1.02442E-03 +/- 7.47E-05 Sv/hr. Error is 7.29E+00 % of the total. Total Ingestion Dose is 2.16695E-06 +/- 1.88E-07 Sv. Error is 8.67E+00 % of the total. Total Inhalation Dose is 5.91653E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.59675E-13 +/- 4.43E-14 kW. Error is 7.91E+00 % of the total. Total Beta Heat Prod is 2.89467E-14 +/- 7.76E-15 kW. Error is 2.68E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58247E+10 1.14E+09 1.191E+03 8.56E+01 5.153E-13 3.70E-14 9.758E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.76E-07 7.186E+00 Y 90m 7.10430E+06 3.98E+06 4.288E+02 2.40E+02 4.683E-14 2.62E-14 4.611E-05 2.58E-05 7.290E-08 4.08E-08 4.288E-08 2.40E-08 5.596E+01 Rb 86 1.37930E+08 3.49E+07 5.936E+01 1.50E+01 7.133E-15 1.81E-15 1.573E-06 3.99E-07 1.662E-07 4.21E-08 5.521E-08 1.40E-08 2.534E+01 Y 90 2.84438E+07 1.59E+07 8.557E+01 4.78E+01 1.280E-14 7.14E-15 6.969E-13 3.89E-13 2.310E-07 1.29E-07 1.284E-07 7.16E-08 5.581E+01 Sr 89 3.59836E+08 1.30E+08 5.709E+01 2.06E+01 5.348E-15 1.93E-15 1.302E-09 4.70E-10 1.484E-07 5.35E-08 4.510E-07 1.63E-07 3.605E+01 Sr 87m 2.75771E+05 1.96E+05 1.886E+01 1.34E+01 1.170E-15 8.31E-16 9.197E-07 6.53E-07 5.657E-10 4.02E-10 3.960E-10 2.81E-10 7.101E+01 H 3 4.44098E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 20 * * * COOLING TIME IS 4.2500E+02 SECS OR 7.0833E+00 MINS * * * ELAPSED TIME IS 36.867 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44098E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37904E+08 1.967E-14 5.935E+01 6.240E-15 0.00E+00 8.918E-16 1.573E-06 1.662E-07 5.520E-08 1.610E+06 Sr 87m 2.67872E+05 3.866E-17 1.832E+01 1.953E-16 0.00E+00 9.416E-16 8.934E-07 5.495E-10 3.846E-10 1.014E+04 Sr 89 3.59812E+08 5.312E-14 5.708E+01 5.347E-15 0.00E+00 7.948E-19 1.302E-09 1.484E-07 4.509E-07 4.369E+06 Y 88 1.58242E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.141E-13 9.758E-04 1.548E-06 5.239E-06 9.213E+06 Y 90 2.85873E+07 4.268E-15 8.600E+01 1.282E-14 0.00E+00 3.958E-17 7.004E-13 2.322E-07 1.290E-07 2.304E+05 Y 90m 6.92436E+06 1.034E-15 4.179E+02 3.110E-15 0.00E+00 4.254E-14 4.495E-05 7.105E-08 4.179E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 4.94398E-08 0.00000E+00 4.87900E-09 9.42174E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.393082E+03 GAMMA BECQUERELS = 4.361900E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.82927E+03 Bq 2.47693E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.82927E+03 Bq 2.47693E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.89230E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.58526E-13 kW TOTAL HEAT PRODUCTION 5.87449E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.87449E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16616E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91587E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16616E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91587E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.4440E-16 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3798E+08 2.2911E-16 1.9683E-14 1.0526E-09 6.2399E-15 1.5044E-10 8.9182E-16 0.0000E+00 0.0000E+00 38 Sr 1.9510E+09 3.2397E-15 2.8539E-13 9.3486E-10 5.5419E-15 1.5898E-10 9.4244E-16 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8915E-09 1.7141E-14 9.3908E-08 5.5669E-13 0.0000E+00 0.0000E+00 40 Zr 2.0020E+05 3.3244E-19 2.9888E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80523E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.48605E+03 Total gammas (per cc per second) 1.88138E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.17175E-02 Gammas per group (per cc per second) 4.18010E+01 ( 0.010- 0.020 MeV) 1.07463E+01 3.58925E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 8.21193E+01 1.64567E+03 ( 0.300- 0.400 MeV) 5.84949E+00 8.37313E+01 ( 0.400- 0.600 MeV) 1.84487E+02 1.84856E+03 ( 0.600- 0.800 MeV) 9.20215E-01 6.58611E+00 ( 0.800- 1.000 MeV) 1.00445E+03 5.59146E+03 ( 1.000- 1.220 MeV) 5.56630E+00 2.51236E+01 ( 1.220- 1.440 MeV) 2.63337E-01 9.91969E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17110E+03 5.94383E+03 ( 2.000- 2.500 MeV) 2.12470E-06 4.73100E-06 ( 2.500- 3.000 MeV) 1.99865E+01 3.64117E+01 ( 3.000- 4.000 MeV) 2.68225E-01 3.83945E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02320E-03 Sieverts/hour ( 1.02320E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8293E+03 Total 5.8745E-13 Total 1.0232E-03 Total 2.1662E-06 Total 5.9159E-06 1 Y 88 1.1906E+03 65.08E+00 Y 88 5.1532E-13 87.72E+00 Y 88 9.7578E-04 95.37E+00 Y 88 1.5478E-06 71.45E+00 Y 88 5.2385E-06 88.55E+00 2 Y 90m 4.1794E+02 22.85E+00 Y 90m 4.5646E-14 77.70E-01 Y 90m 4.4946E-05 43.93E-01 Y 90 2.3221E-07 10.72E+00 Sr 89 4.5094E-07 76.23E-01 3 Y 90 8.6003E+01 47.02E-01 Y 90 1.2863E-14 21.90E-01 Rb 86 1.5727E-06 15.37E-02 Rb 86 1.6619E-07 76.72E-01 Y 90 1.2901E-07 21.81E-01 4 Rb 86 5.9353E+01 32.45E-01 Rb 86 7.1317E-15 12.14E-01 Sr 87m 8.9335E-07 87.31E-03 Sr 89 1.4841E-07 68.51E-01 Rb 86 5.5198E-08 93.31E-02 5 Sr 89 5.7081E+01 31.20E-01 Sr 89 5.3474E-15 91.03E-02 Sr 89 1.3023E-09 12.73E-05 Y 90m 7.1050E-08 32.80E-01 Y 90m 4.1794E-08 70.65E-02 6 Sr 87m 1.8315E+01 10.01E-01 Sr 87m 1.1370E-15 19.35E-02 Y 90 7.0040E-13 68.45E-09 Sr 87m 5.4946E-10 25.37E-03 Sr 87m 3.8463E-10 65.02E-04 7 H 3 7.9111E-04 43.25E-06 H 3 7.2341E-22 12.31E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.34E-07 H 3 2.0569E-13 34.77E-07 8 C 14 2.0054E-05 10.96E-07 C 14 1.5896E-22 27.06E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.69E-08 C 14 1.1631E-13 19.66E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.5853E-13 Total 2.8923E-14 1 Y 88 5.1412E-13 92.05E+00 Y 90 1.2823E-14 44.34E+00 2 Y 90m 4.2536E-14 76.16E-01 Rb 86 6.2399E-15 21.57E+00 3 Sr 87m 9.4165E-16 16.86E-02 Sr 89 5.3466E-15 18.49E+00 4 Rb 86 8.9182E-16 15.97E-02 Y 90m 3.1097E-15 10.75E+00 5 Y 90 3.9580E-17 70.87E-04 Y 88 1.2082E-15 41.77E-01 6 Sr 89 7.9481E-19 14.23E-05 Sr 87m 1.9532E-16 67.53E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 25.01E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 54.96E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.82927E+03 +/- 2.55E+02 Bq. Error is 1.40E+01 % of the total. Total Heat Production is 5.87449E-13 +/- 4.56E-14 kW. Error is 7.77E+00 % of the total. Total Gamma Dose Rate is 1.02320E-03 +/- 7.45E-05 Sv/hr. Error is 7.28E+00 % of the total. Total Ingestion Dose is 2.16616E-06 +/- 1.88E-07 Sv. Error is 8.68E+00 % of the total. Total Inhalation Dose is 5.91587E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.58526E-13 +/- 4.40E-14 kW. Error is 7.87E+00 % of the total. Total Beta Heat Prod is 2.89230E-14 +/- 7.78E-15 kW. Error is 2.69E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58242E+10 1.14E+09 1.191E+03 8.56E+01 5.153E-13 3.70E-14 9.758E-04 7.01E-05 1.548E-06 1.11E-07 5.239E-06 3.76E-07 7.186E+00 Y 90m 6.92436E+06 3.87E+06 4.179E+02 2.34E+02 4.565E-14 2.55E-14 4.495E-05 2.52E-05 7.105E-08 3.98E-08 4.179E-08 2.34E-08 5.596E+01 Rb 86 1.37904E+08 3.49E+07 5.935E+01 1.50E+01 7.132E-15 1.81E-15 1.573E-06 3.98E-07 1.662E-07 4.21E-08 5.520E-08 1.40E-08 2.534E+01 Y 90 2.85873E+07 1.60E+07 8.600E+01 4.80E+01 1.286E-14 7.18E-15 7.004E-13 3.91E-13 2.322E-07 1.30E-07 1.290E-07 7.20E-08 5.581E+01 Sr 89 3.59812E+08 1.30E+08 5.708E+01 2.06E+01 5.347E-15 1.93E-15 1.302E-09 4.70E-10 1.484E-07 5.35E-08 4.509E-07 1.63E-07 3.605E+01 Sr 87m 2.67872E+05 1.90E+05 1.832E+01 1.30E+01 1.137E-15 8.07E-16 8.934E-07 6.34E-07 5.495E-10 3.90E-10 3.846E-10 2.73E-10 7.101E+01 H 3 4.44098E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 21 * * * COOLING TIME IS 6.0800E+02 SECS OR 1.0133E+01 MINS * * * ELAPSED TIME IS 47.000 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44097E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37868E+08 1.967E-14 5.934E+01 6.238E-15 0.00E+00 8.916E-16 1.572E-06 1.661E-07 5.518E-08 1.610E+06 Sr 87m 2.56964E+05 3.708E-17 1.757E+01 1.874E-16 0.00E+00 9.033E-16 8.570E-07 5.271E-10 3.690E-10 1.014E+04 Sr 89 3.59777E+08 5.312E-14 5.708E+01 5.346E-15 0.00E+00 7.947E-19 1.302E-09 1.484E-07 4.509E-07 4.369E+06 Y 88 1.58235E+10 2.310E-12 1.191E+03 1.208E-15 0.00E+00 5.141E-13 9.757E-04 1.548E-06 5.238E-06 9.213E+06 Y 90 2.87843E+07 4.297E-15 8.660E+01 1.291E-14 0.00E+00 3.985E-17 7.052E-13 2.338E-07 1.299E-07 2.304E+05 Y 90m 6.67484E+06 9.965E-16 4.029E+02 2.998E-15 0.00E+00 4.100E-14 4.333E-05 6.849E-08 4.029E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 4.90265E-08 0.00000E+00 4.87330E-09 9.39484E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.393596E+03 GAMMA BECQUERELS = 4.203859E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.81398E+03 Bq 2.45623E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.81398E+03 Bq 2.45623E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.88892E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.56931E-13 kW TOTAL HEAT PRODUCTION 5.85820E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.85820E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16505E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91494E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16505E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91494E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 1.8047E-16 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3794E+08 2.2905E-16 1.9678E-14 1.0523E-09 6.2383E-15 1.5040E-10 8.9159E-16 0.0000E+00 0.0000E+00 38 Sr 1.9517E+09 3.2409E-15 2.8549E-13 9.3343E-10 5.5334E-15 1.5251E-10 9.0409E-16 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8875E-09 1.7117E-14 9.3646E-08 5.5514E-13 0.0000E+00 0.0000E+00 40 Zr 2.5268E+05 4.1958E-19 3.7722E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80312E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.47609E+03 Total gammas (per cc per second) 1.86785E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.15364E-02 Gammas per group (per cc per second) 4.16195E+01 ( 0.010- 0.020 MeV) 1.07286E+01 3.58336E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 7.91601E+01 1.58637E+03 ( 0.300- 0.400 MeV) 5.61127E+00 8.03214E+01 ( 0.400- 0.600 MeV) 1.77928E+02 1.78284E+03 ( 0.600- 0.800 MeV) 8.87054E-01 6.34877E+00 ( 0.800- 1.000 MeV) 1.00441E+03 5.59120E+03 ( 1.000- 1.220 MeV) 5.56484E+00 2.51170E+01 ( 1.220- 1.440 MeV) 2.63325E-01 9.91924E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17100E+03 5.94355E+03 ( 2.000- 2.500 MeV) 2.13935E-06 4.76361E-06 ( 2.500- 3.000 MeV) 1.99856E+01 3.64101E+01 ( 3.000- 4.000 MeV) 2.68213E-01 3.83927E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.02150E-03 Sieverts/hour ( 1.02150E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.8140E+03 Total 5.8582E-13 Total 1.0215E-03 Total 2.1651E-06 Total 5.9149E-06 1 Y 88 1.1905E+03 65.63E+00 Y 88 5.1530E-13 87.96E+00 Y 88 9.7574E-04 95.52E+00 Y 88 1.5477E-06 71.48E+00 Y 88 5.2383E-06 88.56E+00 2 Y 90m 4.0288E+02 22.21E+00 Y 90m 4.4001E-14 75.11E-01 Y 90m 4.3326E-05 42.41E-01 Y 90 2.3381E-07 10.80E+00 Sr 89 4.5090E-07 76.23E-01 3 Y 90 8.6596E+01 47.74E-01 Y 90 1.2952E-14 22.11E-01 Rb 86 1.5723E-06 15.39E-02 Rb 86 1.6615E-07 76.74E-01 Y 90 1.2989E-07 21.96E-01 4 Rb 86 5.9338E+01 32.71E-01 Rb 86 7.1299E-15 12.17E-01 Sr 87m 8.5697E-07 83.89E-03 Sr 89 1.4840E-07 68.54E-01 Rb 86 5.5184E-08 93.30E-02 5 Sr 89 5.7076E+01 31.46E-01 Sr 89 5.3469E-15 91.27E-02 Sr 89 1.3021E-09 12.75E-05 Y 90m 6.8489E-08 31.63E-01 Y 90m 4.0288E-08 68.11E-02 6 Sr 87m 1.7570E+01 96.86E-02 Sr 87m 1.0907E-15 18.62E-02 Y 90 7.0523E-13 69.04E-09 Sr 87m 5.2709E-10 24.35E-03 Sr 87m 3.6896E-10 62.38E-04 7 H 3 7.9111E-04 43.61E-06 H 3 7.2341E-22 12.35E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.35E-07 H 3 2.0569E-13 34.77E-07 8 C 14 2.0054E-05 11.06E-07 C 14 1.5896E-22 27.13E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.72E-08 C 14 1.1631E-13 19.66E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.5693E-13 Total 2.8889E-14 1 Y 88 5.1409E-13 92.31E+00 Y 90 1.2912E-14 44.69E+00 2 Y 90m 4.1003E-14 73.62E-01 Rb 86 6.2383E-15 21.59E+00 3 Sr 87m 9.0330E-16 16.22E-02 Sr 89 5.3461E-15 18.51E+00 4 Rb 86 8.9159E-16 16.01E-02 Y 90m 2.9976E-15 10.38E+00 5 Y 90 3.9853E-17 71.56E-04 Y 88 1.2081E-15 41.82E-01 6 Sr 89 7.9474E-19 14.27E-05 Sr 87m 1.8737E-16 64.86E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 25.04E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 55.02E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.81398E+03 +/- 2.48E+02 Bq. Error is 1.36E+01 % of the total. Total Heat Production is 5.85820E-13 +/- 4.51E-14 kW. Error is 7.71E+00 % of the total. Total Gamma Dose Rate is 1.02150E-03 +/- 7.42E-05 Sv/hr. Error is 7.26E+00 % of the total. Total Ingestion Dose is 2.16505E-06 +/- 1.88E-07 Sv. Error is 8.70E+00 % of the total. Total Inhalation Dose is 5.91494E-06 +/- 4.17E-07 Sv. Error is 7.05E+00 % of the total. Total Gamma Heat Prod is 5.56931E-13 +/- 4.35E-14 kW. Error is 7.81E+00 % of the total. Total Beta Heat Prod is 2.88892E-14 +/- 7.81E-15 kW. Error is 2.70E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58235E+10 1.14E+09 1.191E+03 8.56E+01 5.153E-13 3.70E-14 9.757E-04 7.01E-05 1.548E-06 1.11E-07 5.238E-06 3.76E-07 7.186E+00 Y 90m 6.67484E+06 3.74E+06 4.029E+02 2.25E+02 4.400E-14 2.46E-14 4.333E-05 2.42E-05 6.849E-08 3.83E-08 4.029E-08 2.25E-08 5.596E+01 Rb 86 1.37868E+08 3.49E+07 5.934E+01 1.50E+01 7.130E-15 1.81E-15 1.572E-06 3.98E-07 1.661E-07 4.21E-08 5.518E-08 1.40E-08 2.534E+01 Y 90 2.87843E+07 1.61E+07 8.660E+01 4.83E+01 1.295E-14 7.23E-15 7.052E-13 3.94E-13 2.338E-07 1.30E-07 1.299E-07 7.25E-08 5.581E+01 Sr 89 3.59777E+08 1.30E+08 5.708E+01 2.06E+01 5.347E-15 1.93E-15 1.302E-09 4.69E-10 1.484E-07 5.35E-08 4.509E-07 1.63E-07 3.605E+01 Sr 87m 2.56964E+05 1.82E+05 1.757E+01 1.25E+01 1.091E-15 7.74E-16 8.570E-07 6.09E-07 5.271E-10 3.74E-10 3.690E-10 2.62E-10 7.101E+01 H 3 4.44097E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 * * * TIME INTERVAL 22 * * * COOLING TIME IS 6.0700E+02 SECS OR 1.0117E+01 MINS * * * ELAPSED TIME IS 57.117 m * * * FLUX AMP IS 0.0000E+00 /cm^2/s * * * NUCLIDE ATOMS GRAMS Bq b-Energy a-Energy g-Energy DOSE RATE INGESTION INHALATION HALF LIFE kW kW kW Sv/hr DOSE(Sv) DOSE(Sv) seconds H 3 4.44097E+05 2.224E-18 7.911E-04 7.234E-22 0.00E+00 0.000E+00 0.000E+00 3.323E-14 2.057E-13 3.891E+08 C 14 5.20403E+06 1.210E-16 2.005E-05 1.590E-22 0.00E+00 0.000E+00 0.000E+00 1.163E-14 1.163E-13 1.799E+11 Rb 86 1.37832E+08 1.966E-14 5.932E+01 6.237E-15 0.00E+00 8.914E-16 1.572E-06 1.661E-07 5.517E-08 1.610E+06 Sr 87m 2.46516E+05 3.558E-17 1.686E+01 1.797E-16 0.00E+00 8.666E-16 8.221E-07 5.057E-10 3.540E-10 1.014E+04 Sr 89 3.59742E+08 5.311E-14 5.707E+01 5.346E-15 0.00E+00 7.947E-19 1.302E-09 1.484E-07 4.509E-07 4.369E+06 Y 88 1.58228E+10 2.310E-12 1.190E+03 1.208E-15 0.00E+00 5.141E-13 9.757E-04 1.548E-06 5.238E-06 9.213E+06 Y 90 2.89717E+07 4.325E-15 8.716E+01 1.300E-14 0.00E+00 4.011E-17 7.098E-13 2.353E-07 1.307E-07 2.304E+05 Y 90m 6.43469E+06 9.607E-16 3.884E+02 2.890E-15 0.00E+00 3.953E-14 4.177E-05 6.603E-08 3.884E-08 1.148E+04 0 TOTAL NUMBER OF NUCLIDES PRINTED IN INVENTORY = 8 TOTAL NUMBER OF STABLE NUCLIDES NOT PRINTED = 16 0 TOTAL CURIES TOTAL ALPHA TOTAL BETA TOTAL GAMMA CURIE-MeV CURIE-MeV CURIE-MeV 4.86287E-08 0.00000E+00 4.86763E-09 9.36894E-08 0 ALPHA BECQUERELS = 0.000000E+00 BETA BECQUERELS = 1.394082E+03 GAMMA BECQUERELS = 4.051794E+02 0 TOTAL ACTIVITY FOR ALL MATERIALS 1.79926E+03 Bq 2.43630E-07 Ci/cc DENSITY 5.01E+00 gm/cc TOTAL ACTIVITY EXCLUDING TRITIUM 1.79926E+03 Bq 2.43630E-07 Ci/cc 0 TOTAL ALPHA HEAT PRODUCTION 0.00000E+00 kW TOTAL BETA HEAT PRODUCTION 2.88556E-14 kW TOTAL GAMMA HEAT PRODUCTION 5.55396E-13 kW TOTAL HEAT PRODUCTION 5.84251E-13 kW 0 INITIAL TOTAL MASS OF MATERIAL 1.00000E-03 kg TOTAL HEAT EX TRITIUM 5.84251E-13 kW 0 TOTAL MASS OF MATERIAL 1.00000E-03 kg NEUTRON FLUX DURING INTERVAL 0.00000E+00 n/cm**2/s 0 NUMBER OF FISSIONS 0.00000E+00 BURN-UP OF ACTINIDES 0.00000E+00 % 0 INGESTION HAZARD FOR ALL MATERIALS 2.16396E-06 Sv/kg INHALATION HAZARD FOR ALL MATERIALS 5.91403E-06 Sv/kg 0 INGESTION HAZARD EXCLUDING TRITIUM 2.16396E-06 Sv/kg INHALATION HAZARD EXCLUDING TRITIUM 5.91403E-06 Sv/kg 0 APPM OF He 4 = 5.7692E-07 APPM OF He 3 = 2.1648E-16 APPM OF H 3 = 3.3301E-11 APPM OF H 2 = 4.6139E-08 APPM OF H 1 = 2.1107E-07 COMPOSITION OF MATERIAL BY ELEMENT -------------------------------------- 0 BETA GAMMA ALPHA ATOMS GRAM-ATOMS GRAMS CURIES-MeV kW CURIES-MeV kW CURIES-MeV kW 1 H 3.4306E+09 5.6966E-15 6.7708E-15 1.2203E-16 7.2341E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 2 He 7.6937E+09 1.2776E-14 5.1136E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 6 C 7.5527E+09 1.2542E-14 1.5648E-13 2.6815E-17 1.5896E-22 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 7 N 5.8718E+08 9.7504E-16 1.4626E-14 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 8 O 8.0023E+21 1.3288E-02 2.1260E-01 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 9 F 3.9984E+03 6.6395E-21 1.2614E-19 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 37 Rb 1.3790E+08 2.2899E-16 1.9673E-14 1.0521E-09 6.2367E-15 1.5036E-10 8.9136E-16 0.0000E+00 0.0000E+00 38 Sr 1.9525E+09 3.2421E-15 2.8560E-13 9.3206E-10 5.5253E-15 1.4632E-10 8.6737E-16 0.0000E+00 0.0000E+00 39 Y 5.3335E+21 8.8566E-03 7.8740E-01 2.8835E-09 1.7094E-14 9.3393E-08 5.5364E-13 0.0000E+00 0.0000E+00 40 Zr 3.0542E+05 5.0716E-19 4.5596E-17 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 GAMMA SPECTRUM AND ENERGIES/SECOND ---------------------------------- NEUTRONS PER SECOND ARISING FROM SPONTANEOUS FISSION 0.00000E+00 Entered density (g/cc) 5.01 POWER FROM ALPHA PARTICLES (MeV per Second) 0.00000E+00 POWER FROM BETA PARTICLES (MeV per Second) 1.80102E+02 TOTAL GAMMA POWER FROM ACTIVATION (MeV per Second) 3.46651E+03 Total gammas (per cc per second) 1.85483E+04 GAMMA RAY POWER FROM ACTIVATION DECAY MeV/s ( 0.000- 0.010 MeV) 4.13621E-02 Gammas per group (per cc per second) 4.14448E+01 ( 0.010- 0.020 MeV) 1.07117E+01 3.57769E+03 ( 0.020- 0.050 MeV) 0.00000E+00 0.00000E+00 ( 0.050- 0.100 MeV) 0.00000E+00 0.00000E+00 ( 0.100- 0.200 MeV) 0.00000E+00 0.00000E+00 ( 0.200- 0.300 MeV) 7.63121E+01 1.52929E+03 ( 0.300- 0.400 MeV) 5.38313E+00 7.70556E+01 ( 0.400- 0.600 MeV) 1.71616E+02 1.71959E+03 ( 0.600- 0.800 MeV) 8.55140E-01 6.12036E+00 ( 0.800- 1.000 MeV) 1.00436E+03 5.59095E+03 ( 1.000- 1.220 MeV) 5.56339E+00 2.51104E+01 ( 1.220- 1.440 MeV) 2.63313E-01 9.91878E-01 ( 1.440- 1.660 MeV) 0.00000E+00 0.00000E+00 ( 1.660- 2.000 MeV) 2.17090E+03 5.94328E+03 ( 2.000- 2.500 MeV) 2.15327E-06 4.79463E-06 ( 2.500- 3.000 MeV) 1.99847E+01 3.64084E+01 ( 3.000- 4.000 MeV) 2.68200E-01 3.83910E-01 ( 4.000- 5.000 MeV) 0.00000E+00 0.00000E+00 ( 5.000- 6.500 MeV) 0.00000E+00 0.00000E+00 ( 6.500- 8.000 MeV) 0.00000E+00 0.00000E+00 ( 8.000- 10.000 MeV) 0.00000E+00 0.00000E+00 ( 10.000- 12.000 MeV) 0.00000E+00 0.00000E+00 ( 12.000- 14.000 MeV) 0.00000E+00 0.00000E+00 ( 14.000- 20.000 MeV) 0.00000E+00 0.00000E+00 DOSE RATE (PLANE SOURCE) FROM GAMMAS WITH ENERGY 0-20 MeV IS 1.01986E-03 Sieverts/hour ( 1.01986E-01 Rems/hour) DOMINANT NUCLIDES ----------------- NUCLIDE ACTIVITY PERCENT NUCLIDE HEAT PERCENT NUCLIDE DOSE RATE PERCENT NUCLIDE INGESTION PERCENT NUCLIDE INHALATION PERCENT (Bq) ACTIVITY (kW) HEAT (Sv/hr) DOSE RATE (Sv) INGESTION (Sv) INHALATION Total 1.7993E+03 Total 5.8425E-13 Total 1.0199E-03 Total 2.1640E-06 Total 5.9140E-06 1 Y 88 1.1905E+03 66.16E+00 Y 88 5.1528E-13 88.19E+00 Y 88 9.7569E-04 95.67E+00 Y 88 1.5476E-06 71.52E+00 Y 88 5.2381E-06 88.57E+00 2 Y 90m 3.8838E+02 21.59E+00 Y 90m 4.2418E-14 72.60E-01 Y 90m 4.1767E-05 40.95E-01 Y 90 2.3533E-07 10.88E+00 Sr 89 4.5086E-07 76.23E-01 3 Y 90 8.7160E+01 48.44E-01 Y 90 1.3036E-14 22.31E-01 Rb 86 1.5719E-06 15.41E-02 Rb 86 1.6610E-07 76.76E-01 Y 90 1.3074E-07 22.11E-01 4 Rb 86 5.9322E+01 32.97E-01 Rb 86 7.1280E-15 12.20E-01 Sr 87m 8.2213E-07 80.61E-03 Sr 89 1.4838E-07 68.57E-01 Rb 86 5.5169E-08 93.29E-02 5 Sr 89 5.7070E+01 31.72E-01 Sr 89 5.3464E-15 91.51E-02 Sr 89 1.3020E-09 12.77E-05 Y 90m 6.6025E-08 30.51E-01 Y 90m 3.8838E-08 65.67E-02 6 Sr 87m 1.6855E+01 93.68E-02 Sr 87m 1.0463E-15 17.91E-02 Y 90 7.0982E-13 69.60E-09 Sr 87m 5.0566E-10 23.37E-03 Sr 87m 3.5396E-10 59.85E-04 7 H 3 7.9111E-04 43.97E-06 H 3 7.2341E-22 12.38E-08 0.0000E+00 00.00E+00 H 3 3.3227E-14 15.35E-07 H 3 2.0569E-13 34.78E-07 8 C 14 2.0054E-05 11.15E-07 C 14 1.5896E-22 27.21E-09 0.0000E+00 00.00E+00 C 14 1.1631E-14 53.75E-08 C 14 1.1631E-13 19.67E-07 NUCLIDE GAMMA HEAT PERCENT NUCLIDE BETA HEAT PERCENT (kW) GAMMA (kW) BETA Total 5.5540E-13 Total 2.8856E-14 1 Y 88 5.1407E-13 92.56E+00 Y 90 1.2996E-14 45.04E+00 2 Y 90m 3.9528E-14 71.17E-01 Rb 86 6.2367E-15 21.61E+00 3 Rb 86 8.9136E-16 16.05E-02 Sr 89 5.3456E-15 18.53E+00 4 Sr 87m 8.6657E-16 15.60E-02 Y 90m 2.8898E-15 10.01E+00 5 Y 90 4.0112E-17 72.22E-04 Y 88 1.2081E-15 41.87E-01 6 Sr 89 7.9466E-19 14.31E-05 Sr 87m 1.7975E-16 62.29E-02 7 0.0000E+00 00.00E+00 H 3 7.2341E-22 25.07E-07 8 0.0000E+00 00.00E+00 C 14 1.5896E-22 55.09E-08 UNCERTAINTY ESTIMATES (cross sections only) ------------------------------------------- Uncertainty estimates are based on pathway analysis for the irradiation phase Total Activity is 1.79926E+03 +/- 2.40E+02 Bq. Error is 1.34E+01 % of the total. Total Heat Production is 5.84251E-13 +/- 4.47E-14 kW. Error is 7.65E+00 % of the total. Total Gamma Dose Rate is 1.01986E-03 +/- 7.39E-05 Sv/hr. Error is 7.25E+00 % of the total. Total Ingestion Dose is 2.16396E-06 +/- 1.89E-07 Sv. Error is 8.72E+00 % of the total. Total Inhalation Dose is 5.91403E-06 +/- 4.17E-07 Sv. Error is 7.06E+00 % of the total. Total Gamma Heat Prod is 5.55396E-13 +/- 4.31E-14 kW. Error is 7.75E+00 % of the total. Total Beta Heat Prod is 2.88556E-14 +/- 7.84E-15 kW. Error is 2.72E+01 % of the total. 0 Nuclide Atoms E(Atoms) Activity E(Activity) Heat E(Heat) Dose Rate E(Dose Rate) Ingest E(Ingest) Inhale E(Inhale) % Error Y 88 1.58228E+10 1.14E+09 1.190E+03 8.56E+01 5.153E-13 3.70E-14 9.757E-04 7.01E-05 1.548E-06 1.11E-07 5.238E-06 3.76E-07 7.186E+00 Y 90m 6.43469E+06 3.60E+06 3.884E+02 2.17E+02 4.242E-14 2.37E-14 4.177E-05 2.34E-05 6.603E-08 3.69E-08 3.884E-08 2.17E-08 5.596E+01 Rb 86 1.37832E+08 3.49E+07 5.932E+01 1.50E+01 7.128E-15 1.81E-15 1.572E-06 3.98E-07 1.661E-07 4.21E-08 5.517E-08 1.40E-08 2.534E+01 Y 90 2.89717E+07 1.62E+07 8.716E+01 4.86E+01 1.304E-14 7.28E-15 7.098E-13 3.96E-13 2.353E-07 1.31E-07 1.307E-07 7.30E-08 5.581E+01 Sr 89 3.59742E+08 1.30E+08 5.707E+01 2.06E+01 5.346E-15 1.93E-15 1.302E-09 4.69E-10 1.484E-07 5.35E-08 4.509E-07 1.63E-07 3.605E+01 Sr 87m 2.46516E+05 1.75E+05 1.686E+01 1.20E+01 1.046E-15 7.43E-16 8.221E-07 5.84E-07 5.057E-10 3.59E-10 3.540E-10 2.51E-10 7.101E+01 H 3 4.44097E+05 3.02E+05 7.911E-04 5.38E-04 7.234E-22 4.92E-22 0.000E+00 0.00E+00 3.323E-14 2.26E-14 2.057E-13 1.40E-13 6.795E+01 C 14 5.20403E+06 6.96E+05 2.005E-05 2.68E-06 1.590E-22 2.13E-23 0.000E+00 0.00E+00 1.163E-14 1.55E-15 1.163E-13 1.55E-14 1.337E+01 1 Summary Output 0 Time Cumulative Activity Dose rate Heat output Ingestion dose Inhalation dose Tritium activity (step) (Years) (Bq) (Sv/h) (kW) (Sv) (Sv) (Bq) -----Irradiation Phase----- Irradn 5.000 m 9.51E-06 2.80E+07 +/- 12.5% 9.99E+00 +/- 8.3% 7.14E-09 +/- 7.1% 3.98E-03 +/- 14.0% 2.05E-03 +/- 14.0% 7.91E-04 -----Cooling Phase----- Cooling 1.100 m 2.09E-06 1.41E+06 +/- 13.4% 3.32E-01 +/- 13.4% 2.07E-10 +/- 13.3% 2.17E-04 +/- 13.9% 1.16E-04 +/- 13.3% 7.91E-04 Cooling 16.000 s 2.60E-06 7.17E+05 +/- 13.1% 1.64E-01 +/- 13.4% 1.03E-10 +/- 13.2% 1.08E-04 +/- 13.8% 6.00E-05 +/- 12.7% 7.91E-04 Cooling 16.000 s 3.11E-06 3.73E+05 +/- 12.8% 8.32E-02 +/- 13.1% 5.22E-11 +/- 13.0% 5.43E-05 +/- 13.5% 3.26E-05 +/- 11.6% 7.91E-04 Cooling 27.000 s 3.96E-06 1.34E+05 +/- 12.9% 2.79E-02 +/- 12.4% 1.79E-11 +/- 12.4% 1.80E-05 +/- 12.3% 1.40E-05 +/- 8.6% 7.91E-04 Cooling 37.000 s 5.13E-06 4.31E+04 +/- 17.0% 7.94E-03 +/- 12.3% 5.35E-12 +/- 13.6% 5.30E-06 +/- 8.9% 7.50E-06 +/- 6.3% 7.91E-04 Cooling 34.000 s 6.21E-06 2.11E+04 +/- 22.2% 3.65E-03 +/- 14.4% 2.55E-12 +/- 16.7% 2.89E-06 +/- 7.3% 6.27E-06 +/- 6.7% 7.91E-04 Cooling 53.000 s 7.89E-06 1.05E+04 +/- 24.4% 2.01E-03 +/- 14.2% 1.38E-12 +/- 16.7% 2.26E-06 +/- 8.3% 5.96E-06 +/- 7.0% 7.91E-04 Cooling 1.117 m 1.00E-05 5.72E+03 +/- 21.3% 1.44E-03 +/- 10.3% 9.35E-13 +/- 12.4% 2.18E-06 +/- 8.6% 5.92E-06 +/- 7.0% 7.91E-04 Cooling 1.117 m 1.21E-05 3.67E+03 +/- 16.9% 1.22E-03 +/- 7.9% 7.52E-13 +/- 9.1% 2.17E-06 +/- 8.6% 5.92E-06 +/- 7.0% 7.91E-04 Cooling 1.650 m 1.53E-05 2.46E+03 +/- 13.5% 1.09E-03 +/- 7.1% 6.45E-13 +/- 7.7% 2.17E-06 +/- 8.6% 5.92E-06 +/- 7.0% 7.91E-04 Cooling 2.117 m 1.93E-05 2.01E+03 +/- 13.9% 1.04E-03 +/- 7.2% 6.05E-13 +/- 7.8% 2.17E-06 +/- 8.6% 5.92E-06 +/- 7.0% 7.91E-04 Cooling 2.117 m 2.33E-05 1.90E+03 +/- 14.5% 1.03E-03 +/- 7.3% 5.95E-13 +/- 7.9% 2.17E-06 +/- 8.6% 5.92E-06 +/- 7.0% 7.91E-04 Cooling 2.067 m 2.73E-05 1.87E+03 +/- 14.7% 1.03E-03 +/- 7.3% 5.91E-13 +/- 7.9% 2.17E-06 +/- 8.6% 5.92E-06 +/- 7.0% 7.91E-04 Cooling 3.133 m 3.32E-05 1.86E+03 +/- 14.6% 1.03E-03 +/- 7.3% 5.91E-13 +/- 7.9% 2.17E-06 +/- 8.6% 5.92E-06 +/- 7.1% 7.91E-04 Cooling 4.083 m 4.10E-05 1.85E+03 +/- 14.4% 1.03E-03 +/- 7.3% 5.90E-13 +/- 7.9% 2.17E-06 +/- 8.7% 5.92E-06 +/- 7.1% 7.91E-04 Cooling 4.117 m 4.88E-05 1.85E+03 +/- 14.3% 1.03E-03 +/- 7.3% 5.89E-13 +/- 7.8% 2.17E-06 +/- 8.7% 5.92E-06 +/- 7.1% 7.91E-04 Cooling 4.117 m 5.66E-05 1.84E+03 +/- 14.2% 1.02E-03 +/- 7.3% 5.89E-13 +/- 7.8% 2.17E-06 +/- 8.7% 5.92E-06 +/- 7.1% 7.91E-04 Cooling 7.083 m 7.01E-05 1.83E+03 +/- 14.0% 1.02E-03 +/- 7.3% 5.87E-13 +/- 7.8% 2.17E-06 +/- 8.7% 5.92E-06 +/- 7.1% 7.91E-04 Cooling 10.133 m 8.94E-05 1.81E+03 +/- 13.6% 1.02E-03 +/- 7.3% 5.86E-13 +/- 7.7% 2.17E-06 +/- 8.7% 5.91E-06 +/- 7.1% 7.91E-04 Cooling 10.117 m 1.09E-04 1.80E+03 +/- 13.4% 1.02E-03 +/- 7.2% 5.84E-13 +/- 7.6% 2.16E-06 +/- 8.7% 5.91E-06 +/- 7.1% 7.91E-04 0 Mass of material input = 1.0000E-03 kg. Material density = 5.01 g/cc Total irradiation time = 3.000000E+02 s Total fluence = 3.348000E+12 n/cm2 Mean flux = 1.116000E+10 n/cm2/s Number of on-times = 1 fispact run time= 1.8392 secs ------------------------------------------------------------------ Files that have been opened during this run. ------------------------------------------------------------------ The numbers after the unit names are the internal unit numbers. input( 5) y2o35.i graph(10) y2o35.gra collapxi(12) COLLAPX arrayx(13) ARRAYX hazards(14) /FISPACT-II/decay/hazards_2012 gnuplot(15) y2o35.plt ind_nuc(18) /FISPACT-II/TENDL2017data/tendl17_decay12_index output(38) y2o35.out absorp(39) /FISPACT-II/decay/abs_2012 runlog(48) y2o35.log nucgraph(59) y2o35.grn nucgnu(60) y2o35.pln ------------------------------------------------------------------ Run timestamp:17:44:05 17 September 2019 Current time: 17:44:07 17 September 2019