Converted from EXFOR to X4+ by x4read2x4interp v-2014/04/25, V.Zerkin, IAEA-NDS, 2007-2014
   23114001   20130924   20140113   20140110       2236              
   23114001   20130924   20140113   20140110       2236              
         17        133                                               
 High resolution measurements of the 241Am(n,2n)                      
            reaction cross section                                
 (C.Sage, V.Semkova, O.Bouland, P.Dessagne, A.Fernandez,              
            F.Gunsing, C.Naestren, G.Noguere, H.Ottmar,           
            A.J.M.Plompen, P.Romain, G.Rudolf, J.Somers, F.Wastin)
 (2FR SAC,2ZZZGEL,2FR CAD,2FR STR,3BULBLA,1USALAS,                    
           2ZZZITU,2FR BRC)                                       
 (J,PR/C,81,064604,2010)                                              
           #doi:10.1103/PhysRevC.81.064604                        
           (T,SAGE,141,2009)                                      
           Derivation of full covariance matrix,                  
           Sage's thesis submitted to Univ. Strasbourg.           
 (R,A1007001,H.Liskien+,J,ND/A,11,569,1973)                           
            c.s. used for neutron spectra                         
           (R,,A.B.Smith+,R,ANL-NDM-115,1990)                     
            c.s. for unfolding with 115In(n,n')115In              
           (R,,M.Wagner+,B,PH-DAT,13-5,1990)                      
            c.s. for unfolding with 27Al(n,a) and 93Nb(n,2n)      
           (R,,P.M.Endt,J,NP/A,633,1,1998)                        
            Decay data for A=27                                   
           (R,,Huo Junde,J,NDS,86,315,1999)                       
            Decay data for A=56                                   
           (R,,J.Blachot,J,NDS,104,967,2005)                      
            Decay data for A=115                                  
           (R,,R.B.Firestone,J,NDS,108,2319,2007)                 
            Decay data for A=24                                   
           (R,,C.M.Baglin,J,NDS,91,423,2000)                      
            Decay data for A=92                                   
           (R,,M.R.Bhat,J,NDS,80,789,1997)                        
            Decay data for A=58                                   
 (VDGT,2ZZZGEL) 7-MV Van de Graaff accelerator                        
 Typical beam current on the target 10 uA.                            
           (D-D) 8.34 and 9.15 MeV neutrons by 5.5, 6.3 MeV       
            deuterons using D2 gas target cell of 4 cm length,    
            4 cm diameter, with Mo entrance window at 120 kPa.    
            Samples were placed 1.5 cm from neutron production    
            target.                                               
           (D-T) 16.1 to 20.6 MeV neutrons from solid-state       
            Ti/H-3 target of 2 mg/cm2 thickness on Ag backing of  
            0.4 mm thickness.                                     
            Samples were placed at 0 deg at 2 cm distance from    
            neutron production target.                            
           13.3 MeV neutrons by 1 MeV deuterons.                  
            Sample were placed at 125 deg at 3.9 cm distance from 
            neutron production target.                            
 Quasi-mono-energetic neutron flux 5.E+7 n/sec/cm2.                   
           Mean neutron energy and yield distributions were       
            calculated by code ENERGYSET based on                 
            - cross section evaluations of H.Liskien+ (1973);     
            - energy-loss estimates with stopping powers of       
              H.H.Andersen et al., "Hydrogen stopping powers and  
              ranges in all elements", Pergamon, New York, 1977.  
           To account for contribution of low threshold energies  
            reaction, neutron flux density distributions were     
            determined using previously measured TOF spectra      
            combined with the spectral index method involving     
            various reactions used for unfolding:                 
             115In(n,n')115mIn (A.B.Smith+, 1990),                
             27Al(n,a)24Na (M.Wagner+, 1990),                     
             93Nb(n,2n)92mNb (M.Wagner+, 1990),                   
             27Al(n,p)27Mg (ENDF/B-VI),                           
             56Fe(n,p)56Mn (ENDF/B-VI),                           
             58Ni(n,p)58Co (ENDF/B-VI) .                          
 (HPGE) Pb/Sn/Cu shielding of 5/3/3 mm thickness,                     
            respectively, to reduce 241Am natural activity to     
            limit the dead time of the system to <15% (between    
            7% and 15%, typically).                               
           Co-60 standard source was used to check correctness of 
            dead time given by acquisition system Maestro (Ortec).
           Additional shielding of 10-mm-thick Cu cylinder to     
            avoid detection of scattered gamma-rays.              
           Gamma-ray spectra were analyzed using the software     
            package Genie2000 of Canberra.                        
           Energy calibration was made by standard sources:       
            241Am(59.5 keV), 109Cd(88 keV), 57Co(122.1,136.5 keV),
            137Cs(661.66 keV), 54Mn(834.8 keV), 65Zn(1115.5 keV)  
            for different radial positions and detector-source    
            distance.                                             
           The efficiency was determined by MCNP5 taking into     
            account the entire detection geometry.                
           Results of simulation were compared with measured      
            values and efficiency curves by fitting experimental  
            points with polynomial logarithmic functions.         
           Detector geometry parameters have been optimized to    
            obtain agreement between measurements and simulations 
            within the uncertainty limits.                        
           (BF3) BF3-counter operated in multichannel-scaling     
            acquisition mode - to record the time profile on      
            neutron flux.                                         
 (ACTIV,GSPEC)                                                        
           The intensities of the two main gamma-rays emitted in  
            the decay of 240Am were measured as a function of     
            cooling time after irradiation.                       
 The Am samples were prepared at JRC, ITU, Karlsruhe,                 
            by method based on production of porous alumina       
            granules by powder metallurgy.                        
           Resulting powder was pressed into pellets of 12 mm     
            diameter, 2mm thickness.                              
           Sample weight was on average 400 mg, average Am        
            content was 40 mg. Encapsulated in Al containers.     
           --------------------------------------------------     
            Total mass   241Am content  Al2O3    241Am Calc'd     
             g             mg            g        wt%             
           --------------------------------------------------     
            0.342        32.2+/-0.1     0.305    9.43             
            0.442        42.2+/-0.1     0.394    9.51             
            0.428        40.3+/-0.1     0.382    9.42             
            0.435        41.0+/-0.1     0.388    9.42             
            0.448        41.2+/-0.1     0.401    9.20             
            0.447        42.1+/-0.1     0.399    9.42 .           
           --------------------------------------------------     
           Distance between monitor foils and sample was 3 mm in  
            front, 10 mm at back.                                 
 (13-AL-27(N,A)11-NA-24,,SIG)                                         
 (11-NA-24,14.997HR,DG,1368.6,0.999936)                               
            14.997+/-0.012 hr, 99.9936+/-0.0015%                  
 (,M.Wagner+,B,PH-DAT,13-5,1990)                                      
           (,H.Vonach,R,INDC(SEC)-101,75,1992)                    
 Decay data used for neutron flux unfolding                           
           (12-MG-27,9.458MIN,DG,843.8,0.718)                     
            9.458+/-0.012 min, 71.8+/-0.4%                        
           (25-MN-56,2.5789HR,DG,846.8,0.989)                     
            2.5789+/-0.0001 hr, 98.9+/-0.3%                       
           (49-IN-115-M,4.486HR,DG,336.2,0.46)                    
            4.486+/-0.004 hr, 46+/-2%                             
           (41-NB-92-M,10.15D,DG,934.4,0.9907)                    
            10.15+/-0.02 d, 99.07+/-0.04%                         
           (27-CO-58-G,70.86D,DG,810.8,0.9945)                    
            70.86+/-0.07 d, 99.45+/-0.01%                         
 (APRVD) V.Semkova (2010-10-19)                                       
 (20100924C) M.M.                                                     
           (20120120A) NDS(VZ): REL-REF: ND/B->NDS                
           (20130924U) On. BIB updated                            
ENDBIB             133                                            
NOCOMMON
ENDSUBENT          136                                            
   23114002   20130924   20140113   20140110       2236              
         10         81                                               
 (95-AM-241(N,2N)95-AM-240,,SIG)                                      
 (95-AM-240,50.8HR,DG,987.79,0.722)                                   
            50.8+/-0.3 hr, 987.79+/-0.06 keV, 72.2+/-0.9%         
           The 987.79-keV line is free of interference, while the 
            888.85 keV gamma line is contaminated by the natural  
            activity of the sample itself.                        
           Only 987.79 keV gamma line was used for cross section  
            determination.                                        
 (R,,B.Singh+,J,NDS,109,2439,2008)                                    
            Decay data for A=240                                  
           (R,,M.S.Basunia,J,NDS,107,2323,2006)                   
            Decay data for A=237                                  
           (A,14172003,A.P.Tonchev+,J,PR/C,77,054610,2008)        
           (A,22936002,G.Perdikakis+,J,PR/C,73,067601,2006)       
           (A,41240071,A.A.Filatenkov+,J,PAN,63,1504,2000)        
           (D,13883003,R.W.Lougheed+,J,RCA,90,833,2002)           
 Corrections were done for                                            
           - photon absorption, including the disk shape of the   
             samples and monitor foils, were calculated using     
             MCNP5 simulation of the detection geometry, have     
             been incorporated in the efficiency and were         
             estimated to 0.2% and 1.3%, respectively.            
           - coincidence summings of gamma-rays:                  
              25.4% for 27Al(n,a)  1368.6 keV                     
               0.3% for 27Al(n,p)   843.8 keV                     
              13.5% for 58Ni(n,p)   810.8 keV                     
               0.4% for 93Nb(n,2n)  934.4 keV                     
               9.9% for 56Fe(n,p)   846.8 keV                     
           - neutron flux fluctuations (MISC1,MISC2)              
           - low-energy breakup neutrons (MISC3,MISC4)            
 (MISC1) Flux fluctuation correction factor for Am                    
           (MISC2) Flux fluctuation correction factor for Al      
           (MISC3) Low energy correction factor for Am            
           (MISC4) Low energy correction factor for Al            
 TALYS, ENDF/B-VII, JENDL-3.3 agree each other;                       
           BROND-2.2 close to exp. data only above 18 MeV.        
 (ERR-T,,,P) Total uncertainty                                        
           (MONIT-ERR,,,P) 27Al(n,a) standard x-section (1.6-5.4%)
           (ERR-1,,,U) Counting of 240Am activity       (1.4-6.3%)
           (ERR-2,,,U) Counting of 24Na activity        (0.7-2.0%)
           (ERR-3,,,F) Intensity of 240Am gamma line        (1.2%)
           (ERR-4,,,U) Number of 27Al in sample             (0.1%)
           (ERR-5,,,P) Number of 241Am in sample            (0.3%)
           (ERR-6,,,F) 24Na/240Am efficiency ratio          (3.0%)
           (ERR-7,,,F) Correction for decay of 240Am    (0.4-0.9%)
           (ERR-8,,,U) Correction for secondary neutron    (<1.4%)
  (XY,9,EN,MEV) incident neutron energy                               
             8.34 9.15 13.33 16.10 17.16 17.90 19.36 19.95 20.61  
            (Z,45,COR:ERR-T,PER-CENT) macro-correlation           
             100                                                  
              35 100                                              
              37  42 100                                          
              38  43  53 100                                      
              40  45  57  58 100                                  
              41  45  57  59  84 100                              
              21  24  30  31  39  39 100                          
              30  34  44  45  58  59  51 100                      
              20  22  29  30  40  42  39  65 100                  
            (Z,45,COR:MONIT-ERR,PER-CENT) micro-corr.(standard)   
             100                                                  
              43 100                                              
               0   0 100                                          
               0   0   6 100                                      
               0   0   9  12 100                                  
               0   0   9  12 100 100                              
               0   0  11  11  40  40 100                          
               0   0  11  11  40  40 100 100                      
               0   0  11  11  40  40 100 100 100                  
            (Z,45,COR:ERR-5,PER-CENT) micro-corr. (sample mass)   
             100                                                  
               0 100                                              
               0 100 100                                          
               0 100 100 100                                      
               0   0   0   0 100                                  
             100   0   0   0   0 100                              
               0   0   0   0 100   0 100                          
               0   0   0   0   0   0   0 100                      
             100   0   0   0   0 100   0   0 100                  
 (TABLE) Table V of Phys.Rev.C81(2010)064604,                         
                   Appendix B of Sage's thesis (micro correlation)
 (20130924A) On. ERR-ANALYS, COVARIANCE etc.                          
ENDBIB              81                                            
ERR-3       ERR-4       ERR-5       ERR-6       
PER-CENT    PER-CENT    PER-CENT    PER-CENT    
1.2         .1          .3          3           
ENDCOMMON
EN          EN-ERR      DATA        ERR-T       MONIT-ERR   ERR-1       ERR-2       ERR-7       ERR-8       MISC1       MISC2       MISC3       MISC4       
MEV         MEV         MB          PER-CENT    PER-CENT    PER-CENT    PER-CENT    PER-CENT    PER-CENT    NO-DIM      NO-DIM      NO-DIM      NO-DIM      
8.34        .15         96.8        6.5         1.9         5           1           .9                      .9974       .9925       1           1           
9.15        .15         162.9       5.7         1.9         4           1           .6                      1.0731      1.3117      1           1           
13.33       .15         241.8       4.6         1.6         2.5         1           .4          .3          .9168       .8288       1           1           
16.1        .15         152.4       4.6         2           2.1         1           .6          .3          1.0749      1.2335      1           1           
17.16       .03         116.1       4.4         2           1.5         1           .6          .3          .9987       .9878       .998        .997        
17.9        .1          105.7       4.4         2.2         1.3         .7          .7          .3          .969        .933        .998        .997        
19.36       .15         89.5        8.2         3.1         6.3         2           .6          1.3         1.0061      1.0157      .941        .926        
19.95       .07         102.1       5.8         4.1         1.4         1           .6          1.4         .9822       .9433       .922        .891        
20.61       .04         77.9        8.8         5.4         5.7         1.6         .6          1.4         .9938       .982        .885        .832        
ENDDATA
ENDSUBENT          123                                            
ENDENTRY
   31714001   20130717   20140228   20140212       3162              
   31714001   20130717   20140228   20140212       3162              
         11         66                                               
 Studies of (n,xn) cross-sections in Al, Au, Bi, Cu,                  
           Fe, I, In, Mg, Ni, Ta, Y, and Zn by the activation     
           method                                                 
 (J.Vrzalova,O.Svoboda,A.Krasa,A.Kugler,M.Majerle,                    
            M.Suchopar,V.Wagner)                                  
 (3CZRUJF,3CZRCTI)                                                    
 (J,NIM/A,726,84,2013)                                                
           #doi:10.1016/j.nima.2013.05.133                        
           (J,KPS,59,1709,2011)                                   
           (J,EPJ/CS,8,07003,2010) Data on graphs.                
           (C,2010KRAKOW,,259,2010) Preliminary data on graphs    
           (J,EPJ/CS,21,10007,2012) Additional results for        
           197Au(n,2n), 197Au(n,4n) and 209Bi(n,4n) cross         
           sections at 59.13, 66.54, 72.73, 89.34 MeV. New        
           results for 63Cu(n,3n) reaction.                       
           (C,2012DUBNA,,090,2012) Data on graphs.                
 (P-LI7) High energy protons from the cyclotron were                  
            directed to a thin lithium target.                    
           The neutron flux density was in the range from         
            10**5/cm2/s (TSL) up to 10**8/cm2/s (NPI).            
           Approximately a half of the intensity was in the peak  
            with FWHM = 1 MeV (corresponds to the ground state    
            and first excited state at 0.43 MeV in 7Be) and half  
            of intensity was in the continuum in lower energies   
            (corresponds to higher excited states, multiple-      
            particle emission etc.).                              
           In TSL, proton beams with energies 50, 62, 70, 80,     
            92 and 97 MeV were used.                              
           In NPI, proton beams with energies 20, 32.5, and       
            37 MeV were used.                                     
 (ACTIV) The irradiation times were about 20 h.                       
           Transport times between end of irradiation and         
            activity counting were from 2 minutes in TSL up to    
            15 minutes in NPI.                                    
 (HPGE) The HPGe detectors were calibrated with the                   
            set of laboratory etalons.                            
           Distance between detector-sample was from 10 mm up to  
           173 mm in NPI, respectively 40 mm in TSL               
 The following set of corrections were applied:                       
            - corr. on decay during cooling, irr. and meas.,      
            - self absorption correction,                         
            - non-point like (square) emitter correction,         
            - real gamma-gamma cascade coinc. correction,         
            - detector efficiency and dead time correction,       
            - gamma line intensity correction,                    
            - beam instability correction,                        
            - background subtraction.                             
 (ERR-S,1.,10.) Minimal statistical uncertainty from                  
            the Gauss-fit of the gamma peaks was 1%, but lower    
            than 10% for most of the peaks.                       
           (ERR-1,,3.) Uncertainty of the efficiency of the HPGe  
            detector calibration is below 3%.                     
           (ERR-2) Uncertainty of the neutron beam intensity 10%. 
           (ERR-3,,10.) Uncertainties due to background subtr.    
           (ERR-T) Total uncertainty is a square root of the      
            second powers of Gauss-fit, beam intensity            
            determination and neutron spectrum uncertainties.     
 Decay data were taken from Chu S.Y.F. et al.: The                    
            Lund/LBNL Nuclear Data Search web                     
            Numerical values received from authors.               
 (20110708C) VS                                                       
           (20120626A) VS. New data and new references added:     
             C,2010KRAKOW,,259,2010 and EPJ/CS,21,10007,2012      
             STATUS moved from subent. 001 to 002-017.            
             Subentry 018 added.                                  
           (20130717) VS. Entry revised NIM/A,726,84,2013         
ENDBIB              66                                            
ERR-2       
PER-CENT    
10          
ENDCOMMON
ENDSUBENT           73                                            
   31714008   20130717   20140228   20140212       3162              
          4          6                                               
1(13-AL-27(N,X)11-NA-24,,SIG)                                         
          2(13-AL-27(N,X)11-NA-24,,SIG)                           
1(CYCLO,3CZRUJF)                                                      
          2(CYCLO,2SWDUPP)                                        
 (11-NA-24,14.9590HR,DG,1368.633,1.)                                  
 (TABLE) Data from table 6 of NIM/A 726 (2013) 84.                    
ENDBIB               6                                            
NOCOMMON
EN          EN-ERR      DATA      1 ERR-T     1 DATA      2 ERR-T     2 
MEV         MEV         B           B           B           B           
30.4        .8          .0099       .0014                               
35.9        .8          .0074       .001                                
47          .6                                  .0093       .0014       
59          .4                                  .0181       .0027       
66.4        .4                                  .0194       .0028       
72.8        .4                                  .0174       .0027       
89.3        .7                                  .0148       .0021       
94          .7                                  .0134       .0022       
ENDDATA
ENDSUBENT           21                                            
ENDENTRY
   41328001   19990401   19990705   20050926       0000              
   41328001   19990401   19990705   20050926       0000              
         13         29                                               
 (4RUSFEI)  FIRST FIVE AUTHORS                                        
           (3CUBHAB)  LAST AUTHOR                                 
 (R,INDC(NDS)-272,(131),199203) MAIN REFERENCE                        
                            NUMERICAL DATA AND GRAPHS.            
           (C,88SMOLEN,,272,198806)  EXPERIMENTAL DETAILS, GRAPHS 
           (W,SIMAKOV,199903)  NUMERICAL DATA GIVEN VIA INTERNET  
 (S.P.SIMAKOV, B.V.DEVKIN, M.G.KOBOSEV, A.A.LYCHAGIN,                 
            V.A.TALALAEV, C.SANDIN)                               
 .DIFFERENTIAL NEUTRON EMISSION CROSS-SECTIONS FOR                    
            BERYLLIUM AND TANGSTEN AT 14 MEV INCIDENT NEUTRON     
            ENERGY                                                
 (VDG)  TIME OF FLIGHT SPECTROMETER OF THE                            
            INSTITUTE OF PHYSICS AND POWER ENGINEERING, OBNINSK   
 (TOF) NEUTRON FLIGHT PATH LENGTH WAS 709 CM                          
 (SCIN) NE-218 LIQUID SCINTILLATOR 10 CM IN DAMETER                   
                  AND 5 CM IN LENGTH.                             
 (D-T) 2.5 NSEC PULSED NEUTRONS WERE GENERATED BY                     
                 KLYSTRON NEUTRON GENERATOR KG-0.3 OF IPPE        
 .METALLIC BE-9 (NATURAL ABUNDANCE), HOLLOW CYLINDER:                 
            OUTER DIAMETER 45MM, INNER DIAMETER 30MM, HEIHGT 56MM 
            METALLIC W (NATURAL ABUNDANCE), HOLLOW CYLINDER:      
            OUTER DIAMETER 42MM, INNER DIAMETER 20MM, HEIHGT 50MM 
 .DATA WERE CORRECTED FOR MULTIPLE SCATTERING,                        
            ELASTICALLY SCATTERED NEUTRONS WERE SUBTRACTED        
 (APRVD)   SIMAKOV, 19990326                                          
 (19990331C)  + +   COMPILED AT THE CJD                               
 (ERR-T) TOTAL ERROR                                                  
           (ERR-1) SYSTEMATIC ERROR 6% HAVE TO BE ADDED TO GET    
                   TOTAL ONE                                      
ENDBIB              29                                            
ERR-1       
PER-CENT    
6           
ENDCOMMON
ENDSUBENT           36                                            
   41328002   19990401   19990705   20050926       0000              
          1          1                                               
 (4-BE-9(N,X)0-NN-1,EM,DA/DE)                                         
ENDBIB               1                                            
NOCOMMON
EN          ANG         E           DATA        ERR-T       
MEV         ADEG        MEV         MB/SR/MEV   MB/SR/MEV   
13.45       150         .8          19.9        5.45        
13.45       150         1           11.74       .72         
13.45       150         1.2         11.93       1.04        
13.45       150         1.4         10.24       .63         
13.45       150         1.6         8.01        1.16        
13.45       150         1.8         6.63        .58         
13.45       150         2           6.15        .42         
13.45       150         2.2         5.6         .6          
13.45       150         2.4         5.82        .55         
13.45       150         2.6         4.92        .4          
13.45       150         2.8         3.98        .27         
13.45       150         3           3.88        .24         
13.45       150         3.2         3.8         .27         
13.45       150         3.4         3.9         .32         
13.45       150         3.6         3.71        .46         
13.45       150         3.8         3.63        .32         
13.45       150         4           3.38        .22         
13.45       150         4.2         3.35        .21         
13.45       150         4.4         3.3         .27         
13.45       150         4.6         2.7         .51         
13.45       150         4.8         2.74        .3          
13.45       150         5           2.31        .16         
13.45       150         5.2         1.8         .15         
13.45       150         5.4         1.37        .1          
13.45       150         5.6         1.1         .08         
13.45       150         5.8         .96         .22         
13.45       150         6           1.01        .06         
13.45       150         6.2         1.54        .1          
13.45       150         6.4         2.17        .35         
13.45       150         6.6         3.11        .34         
13.45       150         6.8         5.39        1.2         
13.45       150         7           5.06        .62         
13.45       150         7.2         2.29        .39         
13.72       120         .8          16.06       .96         
13.72       120         1           15.19       1.03        
13.72       120         1.2         13.21       .89         
13.72       120         1.4         11.03       .66         
13.72       120         1.6         9.43        .58         
13.72       120         1.8         7.72        .53         
13.72       120         2           6.41        .52         
13.72       120         2.2         5.27        .32         
13.72       120         2.4         4.77        .29         
13.72       120         2.6         4.24        .25         
13.72       120         2.8         3.93        .35         
13.72       120         3           3.6         .22         
13.72       120         3.2         3.58        .22         
13.72       120         3.4         3.33        .22         
13.72       120         3.6         3.32        .29         
13.72       120         3.8         3.49        .21         
13.72       120         4           3.97        .24         
13.72       120         4.2         4.05        .39         
13.72       120         4.4         3.95        .31         
13.72       120         4.6         3.4         .3          
13.72       120         4.8         3.06        .26         
13.72       120         5           2.49        .21         
13.72       120         5.2         2.14        .18         
13.72       120         5.4         1.94        .14         
13.72       120         5.6         1.87        .15         
13.72       120         5.8         1.72        .12         
13.72       120         6           1.62        .2          
13.72       120         6.2         1.44        .19         
13.72       120         6.4         1.47        .14         
13.72       120         6.6         1.45        .09         
13.72       120         6.8         1.66        .11         
13.72       120         7           2.03        .17         
13.72       120         7.2         3.27        .42         
13.72       120         7.4         4.84        .4          
13.72       120         7.6         5.99        .52         
13.72       120         7.8         5.98        .38         
13.72       120         8           5.12        .62         
13.72       120         8.2         2.78        .52         
13.72       120         8.4         1.32        .25         
13.72       120         8.6         .73         .21         
13.72       120         8.8         .19         .27         
14.1        90          .8          15.37       1.51        
14.1        90          1           13.7        .99         
14.1        90          1.2         12.93       .87         
14.1        90          1.4         11.37       .76         
14.1        90          1.6         10.66       .7          
14.1        90          1.8         9.47        .63         
14.1        90          2           8.05        .54         
14.1        90          2.2         6.47        .45         
14.1        90          2.4         5.8         .41         
14.1        90          2.6         5.11        .37         
14.1        90          2.8         4.33        .34         
14.1        90          3           4           .32         
14.1        90          3.2         3.41        .29         
14.1        90          3.4         3.03        .26         
14.1        90          3.6         2.88        .25         
14.1        90          3.8         2.89        .26         
14.1        90          4           3.08        .26         
14.1        90          4.2         3.22        .28         
14.1        90          4.4         3.32        .28         
14.1        90          4.6         3.6         .3          
14.1        90          4.8         3.87        .29         
14.1        90          5           4.11        .33         
14.1        90          5.2         4.3         .32         
14.1        90          5.4         4.4         .34         
14.1        90          5.6         4.2         .33         
14.1        90          5.8         3.74        .29         
14.1        90          6           3.24        .27         
14.1        90          6.2         2.73        .27         
14.1        90          6.4         2.31        .22         
14.1        90          6.6         2.05        .22         
14.1        90          6.8         1.94        .22         
14.1        90          7           1.94        .21         
14.1        90          7.2         1.5         .26         
14.1        90          7.4         1.47        .2          
14.1        90          7.6         1.51        .19         
14.1        90          7.8         1.38        .25         
14.1        90          8           1.65        .24         
14.1        90          8.2         1.82        .19         
14.1        90          8.4         2.47        .26         
14.1        90          8.6         4.02        .34         
14.1        90          8.8         5.6         .42         
14.1        90          9           5.73        .42         
14.1        90          9.2         6.05        .44         
14.1        90          9.4         6.2         .44         
14.1        90          9.6         4.75        .36         
14.1        90          9.8         2.73        .24         
14.1        90          10          1.25        .29         
14.1        90          10.2        .46         .35         
14.1        90          10.4        .08         .21         
14.49       60          .8          24.29       2.49        
14.49       60          1           17.15       1.38        
14.49       60          1.2         17.24       1.23        
14.49       60          1.4         14.48       1.04        
14.49       60          1.6         13.99       .96         
14.49       60          1.8         12.22       .85         
14.49       60          2           10.61       .75         
14.49       60          2.2         9.65        .69         
14.49       60          2.4         9.36        .66         
14.49       60          2.6         8.44        .63         
14.49       60          2.8         7.12        .56         
14.49       60          3           5.95        .5          
14.49       60          3.2         5.7         .48         
14.49       60          3.4         4.82        .42         
14.49       60          3.6         4.66        .41         
14.49       60          3.8         4.54        .41         
14.49       60          4           4.25        .41         
14.49       60          4.2         4.43        .4          
14.49       60          4.4         3.66        .41         
14.49       60          4.6         3.48        .36         
14.49       60          4.8         3.62        .38         
14.49       60          5           3.65        .37         
14.49       60          5.2         3.55        .39         
14.49       60          5.4         4.04        .4          
14.49       60          5.6         3.94        .39         
14.49       60          5.8         3.99        .39         
14.49       60          6           4.63        .41         
14.49       60          6.2         5.38        .48         
14.49       60          6.4         5.7         .45         
14.49       60          6.6         5.89        .48         
14.49       60          6.8         6.12        .49         
14.49       60          7           5.46        .45         
14.49       60          7.2         4.8         .51         
14.49       60          7.4         4.25        .4          
14.49       60          7.6         4           .47         
14.49       60          7.8         3.89        .38         
14.49       60          8           2.63        .43         
14.49       60          8.2         2.81        .38         
14.49       60          8.4         2.77        .29         
14.49       60          8.6         2.52        .34         
14.49       60          8.8         2.5         .34         
14.49       60          9           2.25        .32         
14.49       60          9.2         2.11        .32         
14.49       60          9.4         2.2         .32         
14.49       60          9.6         2.35        .32         
14.49       60          9.8         2.93        .33         
14.49       60          10          4.41        .4          
14.49       60          10.2        7.1         .54         
14.49       60          10.4        9.09        .65         
14.49       60          10.6        10.56       .73         
14.49       60          10.8        10.41       .72         
14.49       60          11          8.75        .63         
14.49       60          11.2        5.78        .46         
14.49       60          11.4        2.9         .29         
14.49       60          11.6        1.51        .24         
14.49       60          11.8        1.01        .28         
14.49       60          12          .89         .41         
14.49       60          12.2        .76         .57         
14.49       60          12.4        .87         .35         
14.49       60          12.6        .42         .41         
14.78       30          .8          33.1        22.93       
14.78       30          1           27.05       8.28        
14.78       30          1.2         21.41       2.33        
14.78       30          1.4         19.57       2.98        
14.78       30          1.6         16.58       1.59        
14.78       30          1.8         12.76       1.36        
14.78       30          2           15.27       1.4         
14.78       30          2.2         12.27       1.23        
14.78       30          2.4         14.8        1.32        
14.78       30          2.6         17.33       1.43        
14.78       30          2.8         13.98       1.3         
14.78       30          3           10.78       1.13        
14.78       30          3.2         8.59        1           
14.78       30          3.4         9.05        .99         
14.78       30          3.6         7.29        .98         
14.78       30          3.8         6.71        .9          
14.78       30          4           5.64        .86         
14.78       30          4.2         6.42        .92         
14.78       30          4.4         5.23        .99         
14.78       30          4.6         6.51        .87         
14.78       30          4.8         5.52        .89         
14.78       30          5           4.9         .98         
14.78       30          5.2         4.01        .8          
14.78       30          5.4         4.24        .89         
14.78       30          5.6         4.64        .84         
14.78       30          5.8         3.68        .98         
14.78       30          6           4.47        .81         
14.78       30          6.2         5.76        .93         
14.78       30          6.4         5.8         .78         
14.78       30          6.6         4.15        .83         
14.78       30          6.8         4.57        .82         
14.78       30          7           5.59        1.11        
14.78       30          7.2         5.52        .84         
14.78       30          7.4         6.92        .87         
14.78       30          7.6         7.15        1.15        
14.78       30          7.8         6.59        .88         
14.78       30          8           5.27        1.05        
14.78       30          8.2         5.51        .99         
14.78       30          8.4         5.97        .97         
14.78       30          8.6         5.33        .91         
14.78       30          8.8         5.11        .87         
14.78       30          9           4.17        .83         
14.78       30          9.2         3.8         .79         
14.78       30          9.4         3.63        .76         
14.78       30          9.6         3.49        .73         
14.78       30          9.8         3.26        .71         
14.78       30          10          3.29        .69         
14.78       30          10.2        2.61        .67         
14.78       30          10.4        2.91        .66         
14.78       30          10.6        2.97        .65         
14.78       30          10.8        3.1         .65         
14.78       30          11          3.56        .68         
14.78       30          11.2        5.42        .73         
14.78       30          11.4        6.92        .8          
14.78       30          11.6        11.77       1.03        
14.78       30          11.8        15.23       1.21        
14.78       30          12          15.93       1.25        
14.78       30          12.2        11.78       1.02        
14.78       30          12.4        7.57        .81         
14.78       30          12.6        4.49        .64         
14.78       30          12.8        3.71        .6          
14.78       30          13          3.53        2.69        
ENDDATA
ENDSUBENT          253                                            
ENDENTRY