26-FE- 57 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-SEP89 REV2-NOV93
----JENDL-3.2 MATERIAL 2634
-----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
ANGULAR DISTRIBUTIONS FOR MT=16,22,28,91 WERE CONVERTED
FROM THE FILE-6 OF THE JENDL FUSION FILE /5/ (KALBACH'S
SYSTEMATICS)
GAMMA PRODUCTION DATA FOR MT=102 WERE EVALUATED BY S.
IGARASI (NEDAC).
DATA WERE COMPILED BY K. SHIBATA (JAERI).
***** MODIFIED PARTS FOR JENDL-3.2 *********************
(4,16),(4,22),(4,28),(4,91)
OBTAINED FROM JENDL FUSION FILE.
(12,102),(15,102)
STATISTICAL MODEL CALCULATIONS.
********************************************************
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCES
RESONANCE REGION = 1.0E-5 EV TO 200.0 KEV
THE MULTILEVEL BREIT-WIGNER FORMULA WAS USED. PARAMETERS
WERE ADOPTED FROM ALLEN+/1/ FOR S-WAVE RESONANCES, AND
BEER+/2/ FOR P-WAVE RESONANCES IN 0 - 185 KEV.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.
2200-M/S RES. INTEG.
ELASTIC 0.2021 B -
CAPTURE 2.462 B 1.43 B
TOTAL 2.664 B -
MF=3 NEUTRON CROSS SECTIONS
BELOW 200 KEV, BACKGROUND CROSS SECTION WAS GIVEN FOR
THE TOTAL AND CAPTURE CROSS SECTIONS.
ABOVE 200 KEV, THE DATA WERE EVALUATED AS FOLLOWS.
MT=1 TOTAL
SPHERICAL OPTICAL MODEL CALCULATION WAS MADE WITH CASTHY
CODE /3/. PARAMETERS ARE AS FOLLOWS,
V = 46.0-0.25*E , R0=1.286, A0=0.620
WS = 14.08-0.20*E , RS=1.390. AS=0.700
VSO= 6.00 , RSO=1.07,ASO=0.620
(ENERGIES IN MEV UNIT, LENGTHS IN FM UNIT)
MT=2 ELASTIC SCATTERING
GIVEN AS TOTAL MINUS NONELASTIC CROSS SECTIONS
MT=3 NONELASTIC
SUM OF MT=4,16,22,28,102,103,107.
MT=16,22,28,103,107 (N,2N),(N,N'A),(N,N'P),(N,P),(N,A)
CALCULATED WITH GNASH /4/.
MT=4,51-71,91 INELASTIC SCATTERING
THE CASTHY AND GNASH CALCULATIONS WERE ADOPTED FOR
NEUTRON ENERGIES BELOW AND ABOVE 7 MEV, RESPECTIVELY.
THE LEVEL SCHEME USED IS GIVEN AS FOLLOWS:
NO. ENERGY(MEV) SPIN-PARITY
G.S 0.0 1/2 -
1. 0.0144 3/2 -
2. 0.1365 5/2 -
3. 0.3668 3/2 -
4. 0.7064 5/2 -
5. 1.0072 7/2 -
6. 1.1978 9/2 -
7. 1.2654 1/2 -
8. 1.3562 7/2 -
9. 1.6273 3/2 -
10. 1.7254 3/2 -
11. 1.9893 9/2 -
12. 1.9910 1/2 -
13. 2.1180 5/2 -
14. 2.2189 5/2 +
15. 2.3300 1/2 -
16. 2.3560 11/2 -
17. 2.4560 9/2 +
18. 2.5053 5/2 +
19. 2.5643 3/2 -
20. 2.6000 5/2 +
21. 2.6974 1/2 -
CONTINUUM LEVELS WERE ASSUMED ABOVE 2.76 MEV.
MT=102 CAPTURE
CALCULATED WITH CASTHY.
MT=251 MU-BAR
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-71
CASTHY CALCULATION
MT=16,22,28,91
OBTAINED FROM JENDL FUSION FILE (KALBACH'S SYSTEMATICS)
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91
CALCULATED WITH GNASH.
MF=12 PHOTON MULTIPLICITIES AND TRANSITION PROBABILITY ARRAYS
MT=16,22,28,91,103,107
MULTIPLICITIES WERE CALCULATED WITH GNASH.
MT=102
CALCULATED WITH CASTHY.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=16,22,28,51-71,91,102,103,107
ASSUMED TO BE ISOTOPIC.
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=16,22,28,91,103,107
CALCULATED WITH GNASH.
MT=102
CALCULATED WITH CASTHY.
REFERENCES
1) ALLEN B.J. ET AL.: PROC. SPECIALIST MEETING ON NEUTRON
DATA OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL,
P. 476 (1977).
2) BEER H. AND SPENCER R.R.: KFK-2063 (1974).
3) IGARASI S. : J. NUCL. SCI. TECHNOL., 12, 67 (1975).
4) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).
5) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).