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63-Eu-155 ORNL, HEDL EVAL-DEC88 WRIGHT,PRINCE,SCHENTER
DIST-JAN09 20090105
----JEFF-311 MATERIAL 6337
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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** Original data taken from: JEFF-3.1 **
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***************************** JEFF-3.1 *************************
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** Original data taken from: JEFF-3.0 **
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***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- ENDF/B-VI rel.7 (DIST-APR00)
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ENDF/B-VI MOD 3 Revision, March 1998, R.Q. Wright (ORNL)
MF= 2 RESONANCE PARAMETERS
RESOLVED RESONANCE RANGE 1.0-5 to 37.5 eV (revised).
A negative level at -0.50 eV is added and the parameters for
the first positive resonance at 0.603 eV are revised. It
should be noted that the parameters for the 0.603 eV resonance
are now fairly close to those of Anufriev [12].
The revised thermal cross sections are as follows:
2200 m/sec cross sections (barns)
total 3777.90
elastic 17.68
capture 3760.22
Capture resonance integral = 15,288 barns
The capture resonance integral is in good agreement with
the measured value of 15,300 +/- 2,700 barns of Sekine [13].
The thermal capture cross section is also in good agreement
with the Sekine measured value of 3,760 +/- 170 barns.
UNRESOLVED RESONANCE RANGE 37.5 eV to 10 keV (Added)
The following parameters are used in this range:
S0 = 2.3E-4, S1= 0.5E-4, D0 = 4.1875 eV,
GG = 0.094 eV, GG/D0 = 224E-4,
Scattering radius, R = 7.4 fm.
The same scattering radius also used for resolved range.
At 10 keV the calculated cross sections are:
total = 16.02 barns
elastic = 13.71 barns
capture = 2.31 barns
MF= 3 SMOOTH CROSS SECTIONS
MT= 2 Elastic revised to offset change in capture.
MT=102 Capture is reduced above 10 keV; from 1 to 20 MeV
capture is taken to be the same as 153Eu.
Comparison with the previous evaluation is as follows:
Energy Previous Revised
10 keV 4.967 2.311 (barns)
1 MeV 1.389 0.225 (barns)
TOTAL and other partial cross sections unchanged.
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ENDF/B-VI MOD 2 Revision, August 1991, R.Q. Wright (ORNL)
Corrected illegal J-values in file 2.
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ENDF/B-VI MOD 1 Revision, December 1988, R.Q. Wright (ORNL)
The ENDF/B-V 155Eu evaluation, MAT 9832, has been revised
below 35 eV. Resolved resonance parameters are used to define
the total, elastic, and capture cross sections below 35 eV.
Above 35 eV, the evaluation is unchanged from ENDF/B-V.
MF= 2 RESONANCE PARAMETERS
RESOLVED RESONANCE RANGE
The resolved resonance parameters are taken from Mughabghab
[14]. A MLBW (LRF=2) representation was used with the smooth
background set to zero in the resonance region.
The largest contribution to the thermal capture cross
section and to the capture resonance integral is from the first
resonance at 0.603 eV which has a peak capture cross section
(at 300 K) of about 102,000 barns. The thermal capture cross
section is slightly lower than ENDF/B-V, but the capture
resonance integral is higher than the ENDF/B-V value by about
a factor of 12.
2200 m/s capture cross section (barns)
(from resonance parameters) = 3936
Computed resonance integral (barns)
(from resonance parameters) = 23173
above 35 eV = 272
total = 23445
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ENDF/B-V Evaluation, MAT 9832, January 1980, F. Mann and
R. Schenter (HEDL)
ENDF/B-V material converted to ENDF-6 format by NNDC
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ENDF/B-IV Evaluation, MAT 774 December 1979, R. Schenter (HEDL)
and A. Prince (BNL)
BNL,HEDL EVAL-OCT74 A.PRINCE AND R.E. SCHENTER
* * * * * * *
MF=2 RESINANCE PARAMETERS
MT=151 No resonance parameters given except AP.
MF=3 SMOOTH CROSS SECTIONS
MT= 1 Total cross section calculated with a deformed
potential from Moldauer [4] for E > EH.
MT= 2 Elastic cross section from total-capture-inelastic.
E > EH, from 4pi*AP**2 for E < EH.
MT= 4,51,52,.,.,91 Inelastic cross sections calculated
using COMNUC-3 [5]. Level scheme data from Nuclear Data
Tables and Igarasi [6].
MT= 16,17,22,28,103-107 Calculated using THRESH code [7].
MT=102 Neutron capture evaluated using COMNUC-3 and NCAP [1,2]
for E > EH. A 1/v component was added to give the 2200 m/s
cross section of Mughabghab [3] for E < EH.
MF=4 ANGULAR DISTRIBUTIONS
MT= 2 Elastic angular distribution calculated from Moldauer
potential.
MF= 4 Inelastic angular distribution assumed isotropic.
MF=5
MT= 16,17,22,28,91 Energy distributions of secondary neutrons
given as a histogram using calculations of nuclear
temperature from Gilbert [11].
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REFERENCES (CROSS SECTIONS)
1. T. Tamura, report ORNL-4152 (1967)
2. F. Schmittroth, report HEDL TME 73-79 (1973)
3. S.F. Mughabghab and D.I. Garber, report BNL 325, 3 Ed.,
Vol. 1 (1973)
4. P.A. Moldauer, Nucl.Phys. 47, 65 (1963)
5. C.L. Dunford, report AI-AEC-12931 (1970) and private
communication.
6. S. Igarasi (Japan) private communication.
7. S. Pearlstein, J.Nucl.En. 27, 81 (1973)
8. H. Baba and S. Baba, report JAERI 1183 (1969)
9. G. Lautenbach, report RCN-191 (1973)
10. S.M. Zakharova et al., report INDC (CCP)-27/L
11. A. Gilbert and A.G.W. Cameron, Can.J.Phys. 43, 1446 (1965)
12. Anufriev et al., Sov.At.En. 46, 182 (1979)
Data in EXFOR40484.
13. T. Sekine et al., Appl.Rad.Isot. 38, 513 (1987)
14. S.F. Mughabghab, Neutron Cross Sections, Vol. 1, Part B,
Z=61-100 (Academic Press, New York, 1984)
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