26-FE- 56 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-SEP89 REV2-MAR94
----JENDL-3.2 MATERIAL 2631
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 EVALUATION WAS PERFORMED FOR JENDL-3.
87-05 COMPILED BY K.SHIBATA (JAERI).
******JENDL-3.2 *********************************************
93-07 MODFIFCATION WAS MADE FOR (3,51-55),(3,59),(3,91).
FILES 4 AND 5 FOR MT=16,22,28,19 WERE OBTAINED FROM THE
FILE-6 OF THE JENDL FUSION FILE /9/.
DATA FOR (3,4) WERE RECONSTRUCTED.
(3,2) = TOTAL - NONELASTIC
93-11 DATA FOR (12,102) AND (15,102) WERE REEVALUATED BY
S. IGARASI (NEDAC).
94-03 AS FOR (3,2) AND (3,107), SMALL CROSS-SECTION VALUES
WERE REPLACED WITH 0.0.
DATA WERE COMPILED BY K. SHIBATA (JAERI).
*************************************************************
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 FROM THE EXPERIMENTAL DATA BY PEREY+ /1/.
R=6.5 FM WAS SELECTED TO REPRODUCE THE 24-KEV WINDOW CROSS
SECTION. NEUTRON WIDTH OF 27.67-KEV RESONANCE WAS TAKEN AS
1420 EV. THE PARAMETERS OF THE 1.15-KEV RESONANCE WERE
TAKEN FROM THE RESULT OF THE NEANDC TASK FORCE /2/.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.
2200-M/S RES. INTEG.
ELASTIC 12.46 B -
CAPTURE 2.813 B 1.446 B
TOTAL 15.27 B -
MF=3 NEUTRON CROSS SECTIONS
BELOW 250 KEV, BACKGROUND CROSS SECTIONS WERE GIVEN
FOR THE TOTAL AND ELASTIC SCATTERING CROSS SECTIONS.
ABOVE 250 KEV, CROSS SECTIONS WERE EVALUATED AS FOLLOWS.
MT=1 TOTAL
SPHERICAL OPTICAL MODEL CALCULATION WAS MADE BY USING
CASTHY CODE /3/. PARAMETERS ARE AS FOLLOWS,
V = 46.0-0.25*E , R0=1.286, A0=0.620
WS = 14.0-0.20*E , RS=1.390, AS=0.700
VSO= 6.0 , RSO=1.07,ASO=0.620
(ENERGIES IN MEV, LENGTHS IN FM).
MT=2 ELASTIC SCATTERING
GIVEN AS TOTAL MINUS NONELASTIC CROSS SECTIONS.
MT=16,22,28 (N,2N),(N,N'A),(N,N'P)
CALCULATED WITH GNASH /4/.
MT=4,51-77,91 INELASTIC SCATTERING
THE CASTHY AND GNASH CALCULATIONS WERE ADOPTED FOR
NEUTRON ENERGIES BELOW AND ABOVE 7 MEV, RESPECTIVELY.
THE DIRECT-PROCESS COMPONENT WAS CONSIDERED FOR MT=
51,52,53,54,77 BY THE C.C. THEORY.
THE LEVEL SCHEME IS GIVEN AS FOLLOWS:
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1. 0.8468 2 +
2. 2.0851 4 +
3. 2.6576 2 +
4. 2.9417 0 +
5. 2.9600 2 +
6. 3.1200 1 +
7. 3.1229 4 +
8. 3.3702 2 +
9. 3.3884 6 +
10. 3.4454 3 +
11. 3.4493 1 +
12. 3.6009 2 +
13. 3.6019 2 +
14. 3.6070 0 +
15. 3.7480 2 +
16. 3.7558 6 +
17. 3.8320 2 +
18. 3.8565 3 +
19. 4.0940 3 +
20. 4.1003 3 +
21. 4.1200 4 +
22. 4.2982 4 +
23. 4.3020 0 +
24. 4.3950 3 +
25. 4.4010 2 +
26. 4.4584 3 +
27. 4.5100 3 -
CONTINUUM LEVELS WERE ASSUMED ABOVE 4.701 MEV.
***** JENDL-3.2 ****************************************
FOR MF/MT=3/51 BETWEEN THRESHOLD AND 2.1 MEV, EVALUATED
DATA WERE OBTAINED FROM HIGH RESOLUTION DATA OF VOSS ET
AL. /7/ BY TAKING ACCOUNT OF GAMMA-RAY ANGULAR DISTRI-
BUTIONS /8/.
THE CROSS SECTIONS FOR MT=54,91 WERE REPLACED WITH THOSE
CONTAINED IN THE JENDL FUSION FILE.
AS FOR MT=59, A POINT AT 11.7 MEV WAS DELETED.
FURTHERMORE, THE CROSS SECTIONS FOR MT=52-55 WERE MODI-
FIED AROUND THRESHOLD BY CONSIDERING THE MEASUREMENTS
/11,12/.
********************************************************
MT=102 CAPTURE
BELOW 250 KEV, NO BACKGROUND.
THE CASTHY CALCULATION WAS ADOPTED
MT=103 (N,P)
BELOW 7 MEV, BASED ON THE DATA OF SMITH AND MEADOWS/5/.
7 - 13 MEV, TAKEN FROM JENDL-2.
13 - 16 MEV, BASED ON THE DATA OF IKEDA ET AL./6/
16 - 20 MEV, TAKEN FROM JENDL-2.
MT=107 (N,ALPHA)
BASED ON EXPERIMENTAL DATA.
MT=251 MU-BAR
CALCULATED WITH CASTHY /3/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-77
OPTICAL AND STATISTICAL-MODEL CALCULATIONS WERE ADOPTED.
THE C.C. CALCULATIONS WERE ADDED TO THE LEVELS OF MT=51,52,
53,54,77.
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
OBTAINED FROM JENDL FUSION FILE (SINCROS-II/10/ CAL-
CULATIONS).
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=16,22,28,51-77,91,102,103,107
ASSUMED TO BE ISOTROPIC.
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=16,22,28,91,103,107
CALCULATED WITH GNASH.
MT=102
CALCULATED WITH CASTHY.
REFERENCES
1) PEREY F.G. ET AL.: PROC. SPECIALIST MEETING ON NEUTRON DATA
OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, (1977),
P.530.
2) NAKAJIMA Y.: JAERI-M 85-035, P. 196 (1985).
3) IGARASI S. : J. NUCL. SCI. TECHNOL., 12, 67 (1975).
4) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).
5) SMITH D.L. AND MEADOWS J.W.: NUCL. SCI. ENG., 58, 314 (1975).
6) IKEDA Y. ET AL.: JAERI 1312 (1988).
7) VOSS F. ET AL.: PROC. THIRD CONF. ON NEUTRON CROSS SECTIONS
AND TECHNOLOGY, 1971, KNOXVILLE, P.218 (1971).
8) SMITH D.L.: ANL/NDM-20 (1976).
9) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
10) YAMAMURO N.: JAERI-M 90-006 (1990).
11) HOPKINS J.C. AND SILBERT M.G.: NUCL. SCI. ENG.19,431(1964).
12) GILBOY W.B. AND TOWLE J.H.: NUCL. PHYS., 64, 130 (1965).