28-NI- 0 NAIG EVAL-MAR87 S.IIJIMA
DIST-SEP89 REV2-NOV93
----JENDL-3.2 MATERIAL 2800
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 EVALUATION WAS PERFORMED FOR JENDL-3.
87-05 COMPILED BY K.SHIBATA (JAERI).
93-11 JENDL-3.2
GAMMA-RAY PRODUCTION DATA REVISED BY S.IGARASI (NEDAC).
INELASTIC SCATTERING CROSS SECTIONS BY K.SHIBATA(JAERI).
COMPILED BY T.NAKAGAWA (NDC/JAERI).
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,1) 557 KEV - 5 MEV
(3,2)
(3,4), (3,51-91) RE-GROUPING INELASTIC SCATTERINGSIGS.
(3,103), (3,111) SLIGHT MODIFICATION
(4,16) - (4,28), (4,91) FROM JENDL FUSION FILE
(5,16) - (5,91) FROM JENDL FUSION FILE
ALL GAMMA-RAY PRODUCTION DATA
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF NOV. 1993)
EVALUATED AND COMPILED BY S. CHIBA (NDC/JAERI)
CROSS SECTIONS WERE TAKEN FROM JENDL-3.1. HOWEVER, ENERGY
DISTRIBUTIONS OF MT=16, 17, 22, 28 AND 91 WERE REPLACED BY
THOSE CALCULATED WITH SINCROS-II SYSTEM/2/. DDXS OF
CONTINUUM REACTIONS WERE CREATED WITH F15TOB PROGRAM /1/.
THE RATIO OF PRECOMPOUND TO COMPOUND WAS TAKEN FROM
SINCROS-II CALCULATION. KUMABE'S SYSTEMATICS/3/ WAS USED.
OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED IN
THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/. LEVEL
SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/4/.
-------------------------------------------------------------
MF=1,MT=451 COMMENTS AND DICTIONARY
MF=2,MT=151 RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV - 557 KEV
CONSTRUCTED FROM RESONANCE PARAMETERS FOR 5 ISOTOPES WHICH
WERE MAINLY BASED ON THE FOLLOWING DATA:
NI-58 SYME ET AL./5/, JENDL-2/6/
NI-60 PERY ET AL./7,8/
NI-61 JENDL-2/6/, MOXON/9/
NI-62 JENDL-2/6/
NI-64 JENDL-2/6/
CALCULATED 2200 M/S VALUES AND RESONANCE INTEGRALS (BARN):
2200 M/S VALUE RES.INT.
TOTAL 22.241 -
ELASTIC 17.859 -
CAPTURE 4.383 2.143
MF=3 NEUTRON CROSS SECTIONS
BELOW 557 KEV, BACKGROUND CROSS SECTIONS APPLIED TO MT=1, 2 AND
102.
CROSS SECTIONS ABOVE RESONANCE REGION WERE EVALUATED AS FOLLOWS:
MT=1 : TOTAL CROSS SECTION
BASED ON THE HIGH-RESOLUTION DATA OF LARSON+/10/. THE CROSS
SECTION SHAPE WAS UNFOLDED BY CONSIDERING EXPERIMENTAL
RESOLUTION.
MT=2 : ELASTIC SCATTERING
(TOTAL) - (NONELASTIC CROSS SECTIONS).
MT=16,17,22,28,103,104,105,106,107,111: (N,2N),(N,3N),
(N,N'A),(N,N'P),(N,P),(N,D),(N,T),(N,HE-3),(N,A),(N,2P)
CONSTRUCTED FROM ISOTOPIC DATA.
MT=4,51-70,91 : INELASTIC SCATTERING
ISOTOPIC LEVELS WERE GROUPED INTO 20 LEVELS OF NATURAL
ELEMENT. THE CONTRIBUTIONS FROM THE DIRECT PROCESS WERE
TAKEN INTO ACCOUNT FOR THE LEVELS OF MT=56, 59, 60, 61, 62,
63, 69, 70.
MT=102 : CAPTURE
CALCULATED WITH THE STATISTICAL MODEL CODE CASTHY /11/.
MT=251 : MU-BAR
CALCULATED WITH CASTHY /11/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 : CALCULATED WITH OPTICAL MODEL.
MT=16,17,22,28,91 : TAKEN FROM JENDL FUSION FILE.
MT=51-70 : CALCULATED WITH CASTHY. THE DIRECT PROCESS
WAS CONSIDERED FOR MT=56,59,60,61,62,63,69,
70.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,22,28,91 : TAKEN FROM JENDL FUSION FILE.
MF=12 PHOTON MULTIPLICITIES
MT=102 (BELOW 2 MEV)
MULTIPLICITIES OBTAINED FROM ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 2 MEV)
CONSTRUCTED FROM THE DATA OF NI-58 AND NI-60 CALCULATED WITH
GNASH, AND FOLLOWING FACTOR WAS MULTIPLIED BETWEEN 2.0 AND
18.0 MEV, BECAUSE THEY WERE TOO LOW COMPARED WITH EXPERIMENTS
FROM 4.0 TO 16.0 MEV;
F(E)=EXP(0.0042(E-2.0)(18.0-E)).
MT=4 (BELOW 2 MEV)
COMPOSITE DATA FROM LEVEL EXCITATION CROSS SECTIONS AND
BRANCHING RATIOS OF 5 ISOTOPES BELOW 2.0 MEV.
MT=103, 107 (BELOW 2 MEV)
CALCULATED WITH GNASH.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3,4,102,103,107: ISOTROPIC
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=3
CALCULATED WITH GNASH.
MT=102
CALCULATED WITH CASTHY FOR 5 ISOTOPES, TAKING PRIMARY
TRANSITIONS ON NI-58 AND 60, AT 1.0E-5, 2.53E-2, 1.0E+3 AND
1.0E+4 EV.
MT=103, 107
CALCULATED WITH GNASH.
REFERENCES
1) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).
2) YAMAMURO, N.: JAERI-M 90-006 (1990).
3) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).
4) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.
5) SYME D.B. ET AL.: PROC. SPECIALIST'S MEETING ON NEUTRON DATA
OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, 508 DEC.
1977, P.703 (1979).
6) KIKUCHI Y AND SEKINE N.: JAERI-M 85-101 (1985).
7) PEREY F.G. ET AL.: ORNL-5893 (1982).
8) PEREY C.M. ET AL.: PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC
AND APPLIED SCIENCE, SANTA FE, 13-17 MAY 1985, P.1639 (1986).
9) MOXON M.C.: KFK-2046, P.156 (1975).
10) LARSON D.C. ET AL.: ORNL-TM-8203 (1983).
11) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).