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9.323800+4 2.360060+2 1 1 2 0
0.000000+0 1.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 109 1
93-Np-238 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 9349
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
ENDF/B-VI.4 (MF1MT452,455,456 MF5MT455)
******************************************************************
******************************************************************
* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=8338). *
******************************************************************
* 21-DEC-84: RADIOACTIVE DECAY DATA DELETED.
* 28-AUG-85: MISSING ISOTROPIC ANG. DISTR. FOR FISSION INSERTED
* 30-OCT-86: CROSS SECTION DATA ABOVE 10 KEV AND ALL MT=4,16,17
* AND 91 REPLACED BY DATA FROM THE ENDL84 LIBRARY.
* 5-APR-88: CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
* BREIT-WIGNER RESONANCE PARAMETERS.FOR THE SPIN OF
* L=0,RESONANCES HAVE BEEN RANDOMLY ASSIGNED BY THE
* COMPUTER CODE RNDSPIN (H. GRUPPELAAR)
******************************************************************
SRL EVAL-AUG75-BENJAMIN AND MCCROSSON
DIST-DEC78 790307
FILES CONVERTED TO ENDF/B-V FORMAT AND DECAY DATA MERGED AT
BNL BY R. KINSEY
* * * * * *
NEPTUNIUM-238 EVALUATION AUGUST 1975 - R.W.BENJAMIN AND
F.J.MCCROSSON AT SRL
MF=1 GENERAL INFORMATION
MT=452 NUBAR THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK
OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND
KONSHIN(REF.2). ENERGY DEPENDENCE BASED ON WORK OF HOWER-
TON(REF.3).
MF=2 RESONANCE PARAMETERS(0 TO 10 KEV)
MT=151 RESOLVED RESONANCES RESONANCE PARAMETERS DETERMINED BY
THE GENRPAR CODE(REF.4) BASED UPON THE SRL DATA SET AND AN
AVERAGE LEVEL SPACING OF 1.05 EV. RESOLVED REGION - 0 TO
100.2 EV.
UNRESOLVED RESONANCES SAME BASIS AS RESOLVED WITH
AVERAGE RESONANCE PARAMETERS. UNRESOLVED REGION - 100.2 EV
TO 10 KEV.
CROSS SECTION SIGMA(0.0253 EV) I(0.5 EV - 20 MEV)
TOTAL 2250.99
ELASTIC 21.25
FISSION 2026.90 895.60
CAPTURE 202.83 100.03
MF=3 SMOOTH CROSS SECTIONS(0 TO 20 MEV)
*** THE DATA IN FILE 3 ARE GIVEN ONLY SO THAT THE VARIOUS
PROCESSING CODES CAN WORK. CONTINUITY WITH THE UNRESOLVED
REGION IS PROVIDED, BUT THE CROSS SECTIONS DROP IMMEDIATELY
TO ZERO. THE ELASTIC SCATTERING CROSS SECTION ABOVE 10 KEV
IS THE POTENTIAL SCATTERING CROSS SECTION CALCULATED WITH A
SPHERICAL OPTICAL MODEL POTENTIAL AT 10 KEV.
MF=4 ANGULAR DISTRIBUTIONS
MT=2 ELASTIC
DISTRIBUTIONS TAKEN FROM ENDF/B-V U-238
MF=5 SECONDARY NEUTRON ENERGY DISTRIBUTIONS
MT=18 FISSION SIMPLE FISSION MAXWELLIAN WITH ENERGY-DEPENDENT
TEMPERATURE.
REFERENCES
1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.
2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.
3. R.J.HOWERTON,NUCL.SCI.ENG.46(1971)42.
4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,
KNOXVILLE,TN,MARCH 1971,P.714.
******************************************************************
Relevant comments from ENDF/B-VI.4
----------------------------------
ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC
* * * * * * *
FILES CONVERTED TO ENDF/B-V FORMAT AND DECAY DATA MERGED AT
BNL BY R. KINSEY
* * * * * *
NEPTUNIUM-238 EVALUATION AUGUST 1975 - R.W.BENJAMIN AND
F.J.MCCROSSON AT SRL
MF=1 GENERAL INFORMATION
MT=452 NUBAR THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK
OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND
KONSHIN(REF.2). ENERGY DEPENDENCE BASED ON HOWERTON (REF.3)
MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989)
MF=5 SECONDARY NEUTRON ENERGY DISTRIBUTIONS
MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989)
REFERENCES
1. L.D.GORDEEVA AND G.N.SMIRENKIN,SOV.AT.EN.14(1963)56.
2. F.MANERO AND V.A.KONSHIN,AT.EN.REV.10(1972)637.
3. R.J.HOWERTON,NUCL.SCI.ENG.46(1971)42.
4. F.J.MCCROSSON,PROC.CONF.NEUT.CROSS SECTIONS AND TECH.,
KNOXVILLE,TN,MARCH 1971,P.714.
******************************************************************
1 451 114
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