26-FE- 54 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-SEP89 REV2-NOV93
----JENDL-3.2 MATERIAL 2625
-----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
THE CROSS SECTIONS FOR MT=54,55 WERE MODIFIED BY
K. SHIBATA (JAERI).
THE Q-VALUE OF MT=102 WAS CORRECTED.
ANGULAR DISTRIBUTIONS FOR MT=16,22,28,91 WERE OBTAINED
FROM THE JENDL FUSION FILE /8/ (KALBACH'S SYSTEMATICS).
THE GAMMA PRODUCTION DATA WERE REEVALUATED BY S. IGARASI
(NEDAC).
DATA WERE COMPILED BY K. SHIBATA.
***** MODIFIED PARTS FOR JENDL-3.2 *******************
(3,54),(3,55) DIRECT COMPONENTS
(3,102) Q-VALUE CORRECTED
(3,4) RECALCULATED
(3,2) TOTAL - NONELASTIC
(4,16),(4,22),(4,28),(4,91)
CONVERTED FROM JENDL FUSION FILE
(12,28),(12,102),(12,103)
MULTIPLICITIES CORRECTED
(15,102) NEWLY CALCULATED BELOW 10 KEV
*******************************************************
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 250.0 KEV
THE MULTILEVEL BREIT-WIGNER FORMULA WAS USED. PARAMETERS
WERE ADOPTED MAINLY FROM PANDEY+/1/ BY ASSUMING THE AVERAGE
RADIATIVE WIDTH TO BE 2.5 EV /2/. R=5.6 FM WAS TAKEN FROM
REF. /3/.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.
2200-M/S RES. INTEG.
ELASTIC 0.4929 B -
CAPTURE 2.156 B 1.33 B
TOTAL 2.649 B -
MF=3 NEUTRON CROSS SECTIONS
BELOW 250 KEV, BACKGROUND CROSS SECTIONS WERE GIVEN FOR THE
TOTAL AND ELASTIC SCATTERING CROSS SECTIONS ON THE UPPER
SIDE OF THE FIRST RESONANCE. ABOVE 250 KEV, THE CROSS
SECTIONS WERE EVALUATED AS FOLLOWS.
MT=1 TOTAL
SPHERICAL OPTICAL MODEL CALCULATION WAS MADE BY USING CODE
CASTHY /4/. OPTICAL POTENTIAL PARAMETERS ARE AS FOLLOWS:
V = 46.0-0.250*E , R0=1.286, A0=0.620
WS = 14.00-0.200*E , RS=1.390, AS=0.700
VSO= 6.00 , RSO=1.070,ASO=0.620
(ENERGIES IN MEV, LENGTHS IN FM)
MT=2 ELASTIC SCATTERING
GIVEN AS TOTAL MINUS OTHER CROSS SECTIONS
MT=16,22,28 (N,2N),(N,N'A),(N,N'P)
CALCULATED USING THE GNASH CODE /5/.
MT=4,51-69,91 INELASTIC SCATTERING
BELOW 7 MEV, THE CROSS SECTIONS WERE CALCULATED USING
CASTHY WITH WIDTH FLUCTUATION CORRECTIONS.
ABOVE 7 MEV, THE GNASH CALCULATION WAS PERFORMED.
FOR MT=51,52,53,55,59,68, THE DIRECT PROCESS
COMPONENT WAS CONSIDERED BY THE C.C. THEORY.
LEVEL SCHEME IS GIVEN AS FOLLOWS:
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1. 1.4082 2 +
2. 2.5382 4 +
3. 2.5613 0 +
4. 2.9499 6 +
5. 2.9590 2 +
6. 3.1661 2 +
7. 3.2952 4 +
8. 3.3450 3 -
9. 3.8338 4 +
10. 4.0330 4 +
11. 4.0472 4 +
12. 4.0720 3 +
13. 4.2632 4 +
14. 4.2961 0 +
15. 4.5980 2 +
16. 4.6550 2 +
17. 4.7000 3 +
18. 4.7800 3 -
19. 4.9490 4 +
CONTINUUM LEVELS WERE ASSUMED ABOVE 5.145 MEV.
MT=102 CAPTURE
CASTHY CALCULATION WAS ADOPTED.
MT=103 (N,P)
BELOW 2.5 MEV, BASED ON THE DATA OF PAULSEN AND WIDERA/6/.
BETWEEN 2.5 AND 10 MEV, BASED ON THE DATA OF SMITH AND
MEADOWS/7/.
ABOVE 10 MEV, CALCULATED WITH GNASH.
MT=107 (N,ALPHA)
GNASH CALCULATION MULTIPLIED BY 0.94.
MT=251 MU-BAR
CALCULATED WITH CASTHY /4/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-69
OPTICAL AND STATISTICAL-MODEL CALCULATION.
FOR MT=51,52,53,54,59,68, THE DIRECT-PROCESS COMPONENT
WAS TAKEN INTO ACCOUNT BY THE C.C. THEORY.
MT=16,22,28,91
CONVERTED FROM THE FILE-6 OF THE JENDL FUSION FILE/8/.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91
CALCULATED WITH GNASH.
MF=12 PHOTON MULTIPLICITIES AND TRANSITION PROBABILITY ARRAYS
MT=16,22,28,91,102,103,107
MULTIPLICITIES WERE CALCULATED WITH GNASH.
FOR MT=28,102,103, CORRECTIONS WERE MADE.
MT=51-69
TRANSITION PROBABILITY ARRAYS
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=16,22,28,51-69,91,102,103,107
ASSUMED TO BE ISOTROPIC.
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=16,22,28,91,102,103,107
CALCULATED WITH GNASH.
FOR MT=102, REPLACED WITH NEW CALCULATIONS BELOW 10 KEV.
REFERENCES
1) PANDEY M.S. ET AL.: PROC. CONF. NUCLEAR CROSS SECTIONS AND
TECHNOLOGY, WASHINGTON D.C., (1975), P.748.
2) SPENCER R.R. AND BEER H.: KFK 2046, 79 (1975).
3) MUGHABGHAB S.F. AND GARBER D.I.: BNL 325, 3RD ED. VOL. 1
(1973).
4) IGARASI S. : J. NUCL. SCI. TECHNOL., 12, 67 (1975).
5) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).
6) PAULSEN A. AND WIDERA R.: PROC. CONF. CHEMICAL NUCLEAR DATA,
MEASUREMENTS AND APPLICATION, CANTERBURY, 1971.
7) SMITH D.L. AND MEADOWS J.W.: NUCL. SCI. ENG., 58, 314 (1975).
8) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).