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