92-U -232 KINKI U.+ EVAL-MAR87 T.OHSAWA AND T. NAKAGAWA
DIST-SEP89 REV2-MAR94
----JENDL-3.2 MATERIAL 9219
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 EVALUATION WAS CARRIED OUT BY T. OHSAWA (KINKI UNIVERSITY)
AND T. NAKAGAWA (JAERI).
T.NAKAGAWA: RESONANCE PARAMETERS
T.OHSAWA : OTHER QUANTITIES
COMPILATION WAS MADE BY T.NAKAGAWA (JAERI).
94-03 JENDL-3.2
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,102) ONLY Q-VALUE WAS MODIFIED.
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MT=452 TOTAL NUMBER OF NEUTRONS PER FISSION
SUM OF NU-P AND NU-D
MT=455 NUMBER OF DELAYED NEUTRONS
DETERMINED FROM TUTTLE'S SEMI-EMPIRICAL FORMULA /1/.
MT=456 NUMBER OF PROMPT NEUTRONS
BASED ON THE SEMI-EMPIRICAL FORMULA BY BOIS AND FREHAUT /2/.
MF=2, MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCE PARAMETERS (FROM 1.0E-5 TO 200 EV)
RECOMMENDATION BY MUGHABGHAB /3/ WAS ADOPTED, AND ITS FORMULA
WAS CHANGED FROM REICH-MOORE TO MULTILEVEL BREIT- WIGNER
TYPE. BACKGROUND CROSS SECTION WAS GIVEN TO REPRODUCE
MEASURED FISSION CROSS SECTIONS /4,5/ AT VALLEYS OF LEVELS.
CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200-M/S RES. INTEG.
TOTAL 162.3 B
ELASTIC 10.79 B
FISSION 76.66 B 364 B
CAPTURE 74.88 B 173 B
THESE VALUES ARE ALMOST THE SAME AS RECOMMENDATION
BY MUGHABGHAB/3/ EXCEPT CAPTURE RESONANCE INTEGRAL
WHICH IS RECOMMENDED AS 280+-15 BARNS.
MF=3 NEUTRON CROSS SECTIONS
ABOVE 200 EV
MT=1 TOTAL
CALCULATED WITH THE SPHERICAL OPTICAL MODEL.
THE PARAMETERS FOR THE SPHERICAL OPTICAL PARAMETERS WERE
AS FOLLOWS:
V = 40.47 - 0.06*EN (MEV), VSO = 8.8 (MEV)
WS = 6.8 + 0.04*SQRT(EN) (MEV), WV = 0.0
R = 1.32 (FM), RS = 1.38 (FM), RSO = 1.22 (FM)
A = AS = ASO = 0.47 (FM),
THIS SET OF PARAMETERS WAS FOUND TO GIVE GOOD AGREEMENT
WITH THE MEASUREMENTS OF SIMPSON ET AL./6/ IN THE ENERGY
REGION FROM 1 KEV TO 10 KEV.
MT=2 ELASTIC SCATTERING
CALCULATED WITH THE CODE CASTHY/7/.
MT=16 (N,2N)
CALCULATED WITH THE MODEL OF SEGEV-FAHIMA/8/.
MT=17 (N,3N)
CALCULATED WITH THE MODEL OF SEGEV-FAHIMA/8/.
MT=18 FISSION
CALCULATED BY USING THE FISSION PROBABILITY DATA OF
GAVRON ET AL./9/ AND COMPOUND FORMATION CROSS SECTIONS
CALCULATED WITH THE OPTICAL MODEL. BELOW 1 KEV, THE CROSS
SECTION WAS DETERMINED ON THE BASIS OF FARRELL /5/.
MT=51-60,91 INELASTIC SCATTERING TO THE DISCRETE AND CON-
TINUOUS LEVELS
CALCULATED WITH THE CODE CASTHY/7/. THE LEVEL SCHEME WAS
TAKEN FROM LEDERER ET AL./10/ AND SCHMORAK/11/.
NO. ENERGY(MEV) SPIN-PARITY
GS 0.0 0+
1 0.048 2+
2 0.157 4+
3 0.323 6+
4 0.541 8+
5 0.563 1-
6 0.629 3-
7 0.692 0+
8 0.736 2+
9 0.805 10+
10 0.867 2+
CONTINUUM REGION WAS ASSUMED ABOVE 1.0 MEV. THE LEVEL
DENSITY PARAMETERS OF GILBERT-CAMERON/12/ WERE USED.
MT=102 CAPTURE
CALCULATED WITH THE CODE CASTHY/7/.
MT=251 MU-BAR
CALCULATED WITH THE CODE CASTHY/7/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 ELASTIC SCATTERING
CALCULATED WITH THE CODE CASTHY/7/.
MT=51-60,91 INELASTIC SCATTERING
CALCULATED WITH THE CODE CASTHY/7/.
MT=16,17 (N,2N), (N,3N)
ASSUMED TO BE ISOTROPIC IN THE LAB SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF THE SECONDARY NEUTRONS
MT=16,17 91 (N,2N), (N,3N) AND CONTINUUM INELASTIC
EVAPORATION SPECTRA.
MT=18 FISSION
MAXWELL SPECTRUM. THE TEMPERATURE PARAMETERS WERE ESTI-
MATED FROM THE SYSTEMATICS OF HOWERTON-DOYAS/13/.
REFERENCES
1) TUTTLE,R.J.: INDC(NDS)-107/G, P.29 (1979).
2) BOIS,R. AND FREHAUT,J.: CEA-R-4791 (1976).
3) MUGHABGHAB,S.F.: "NEUTRON CROSS SECTIONS", VOL.1, PART B,
ACADEMIC PRESS (1984).
4) AUCHAMPAUGH,G.F., ET AL.: NUCL. PHYS., A112, 329 (1968).
5) FARRELL,J.A.: LA-4420,3 (1970). DATA = EXFOR 10055002.
6) SIMPSON,O.D., ET AL.: NUCL. SCI. ENG. 29, 415 (1967).
7) IGARASI,S. AND FUKAHORI,T.: JAERI 1321 (1991).
8) SEGEV,M. AND FAHIMA,Y.: ANN. NUCL. ENERGY 7, 557 (1980).
9) GAVRON,A. ET AL.: PHYS. REV. C13, 2374 (1976).
10) LEDERER,C.M., ET AL.: TABLE OF ISOTOPES (1978), P.1422
11) SCHMORAK,M.K.: NUCL. DATA SHEETS 20, NO.2 (1977).
12) GILBERT,A. AND CAMERON,A.G.: CAN. J. PHYS. 43, 1446 (1965).
13) HOWERTON,R.J. AND DOYAS,R.J.: NUCL. SCI. ENG. 46, 414 (1971).