2.805900+4 5.842810+1 1 0 2 0
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 60 1
28-Ni- 59 NEA/ECN RCOM-NOV87 GRUPPELAAR,VD.KAMP,KOPECKY,NIEROP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 2828
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
Skeleton MF-5 MT-16,22,28,32,34 added
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
******************************************************************
HISTORY
89-01 EVALUATION COMPILED AT THE NEA DATA BANK.
90-01 PHOTON PRODUCTION ADDED (ECN). DATA FROM THE 60-NI JEF-2
EVALUATION USED AS AN ESTIMATE (SEE REF. /1/).
MF=2
MT=151 RESONANCE PARAMETERS TAKEN FROM BNL-325 (4TH ED.)
MF=3
MT=1 BACKGROUND CROSS SECTION IN THE RESONANCE REGION TAKEN
FROM THE SUM OF MT=103 AND MT=107, AS TWO COMPETITIVE
ARE NOT ALLOWED IN THE ENDF FORMAT.
THE HIGH ENERGY REGION WAS CONSTRUCTED AS THE SUM OF
ALL PARTIAL CROSS SECTIONS.
MT=2 HIGH ENERGY REGION GIVEN AS A STRAIGHT LINE BETWEEN THE
VALUE AT THE END OF THE RESONANCE REGION (13 B) AND AN
ESTIMATED VALUE OF 1 BARN AT 20 MEV.
MT=103 TAKEN FROM KEDAK4.
MT=107 TAKEN FROM KEDAK4.
ALL OTHER CROSS SECTIONS TAKEN FROM THE ACTIVATION LIB.
REAC-ECN-4.
MF=4
MT=2 TAKEN FROM NI-61 EVALUATION OF JENDL-2
ALL OTHER ANGULAR DISTRIBUTIONS ASSUMED TO BE ISOTROPIC
MF=12 PHOTON MULTIPLICITIES
MT=3 LUMPED PHOTON PRODUCTION ABOVE 1 MEV (MAURINA CODE)
MT=102 (N,G) REACTION BELOW 1 MEV (GNASH CODE)
MF=14 ANGULAR DISTRIBUTIONS
MT=3,102 ASSUMED ISOTROPIC IN CM SYSTEM
MF=15 ENERGY DISTRIBUTION
MT=3 NORMALIZED ENERGY DISTRIBUTIONS (EN > 1 MEV).
MT=102 NORMALIZED ENERGY DISTRIBUTIONS (EN < 1 MEV).
REFERENCES:
/1/ H. GRUPPELAAR, H. V.D. KAMP, J. KOPECKY, D. NIEROP AND
M. UHL,"EVALUATION OF NEUTRON CROSS-SECTIONS AND
PHOTON-PRODUCTION DATA FOR NI-ISOTOPES IN THE ENERGY RANGE
0 - 20 MEV", JEF-DOC (1990), ECN-REPORT, ECN-90.
1 451 65
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