96-Cm-249
96-CM-249 JAERI EVAL-MAR84 Y.KIKUCHI AND T.NAKAGAWA
JAERI-M 84-116 DIST-SEP89 REV2-SEP92
----JENDL-3.2 MATERIAL 9652
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
84-03 NEW EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND
T.NAKAGAWA (JAERI). DETAILS ARE GIVEN IN REF. /1/.
92-09 JENDL-3.2
COMPILED BY T.NAKAGAWA
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(5,18) VALUE OF ZA WAS CORRECTED.
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENTS AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT=455 AND MT=456.
MT=455 NUMBER OF DELAYED NEUTRONS PER FISSION
SEMI-EMPIRICAL FORMULA BY TUTTLE /2/.
MT=456 NUMBER OF NEUTRONS PER FISSION
SEMI-EMPIRICAL FORMULA BY HOWERTON /3/.
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS
1/V REGION : 1.0E-5 TO 4.15 EV
NO RESOLVED RESONANCES WERE GIVEN.
UNRESOLVED RESONANCE REGION : 4.15 EV TO 30 KEV
OBTAINED FROM OPTICAL MODEL CALCULATION:
S0=1.08E-4, S1=3.95E-4, S2=1.04E-4, R=8.8 FM.
ESTIMATED FROM LEVEL DENSITY PARAMETERS AND SYSTEMATICS
D-OBS=8.3 EV, GAM-G=40 MILLI-EV
GAM-F OBTAINED BY FITTING THE ESTIMATED FISSION CROSS
SECTION(SEE BELOW).
2200 M/S CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 13.22 B -
ELASTIC 10.80 B -
FISSION 0.820 B 139 B
CAPTURE 1.600 B 215 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 4.15 EV, POINTWISE CROSS SECTIONS WERE GIVEN AS
FOLLOWS:
MT=1(TOTAL) : SUM OF PARTIAL CROSS SECTIONS,
MT=2(ELASTIC SCAT.): 10.8 B CALCULATED WITH OPTICAL MODEL,
MT=18(FISSION) : 1/V SHAPE(0.82 B AT 0.0253 EV ESTIMATED
FROM RATIO OF FISSION AND CAPTURE CROSS
SECTIONS IN UNRESOLVED RESONANCE REGION),
MT=102(CAPTURE) : 1/V SHAPE (1.6 B AT 0.0253 EV
OBTAINED FROM MEASUREMENTS BY DIAMOND/4/)
BETWEEN 4.15 EV AND 30 KEV, CROSS SECTIONS WERE REPRESENTED
WITH RESONANCE PARAMETERS.
MT=1,2,4,51-57,91,102,251 TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTIONS AND MU-L
CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE
CASTHY/5/.
THE SPHERICAL OPTICAL POTENTIAL PARAMETERS (MEV,FM):
V =43.4-0.107*EN, R =1.282, A =0.60
WS =6.95-0.339*EN+0.0531*EN**2, RS =1.29, B =0.50
(DERIVATIVE WOODS-SAXON FORM)
VSO=7.0, RSO=1.282, ASO=0.60
THIS SET OF POTENTIAL PARAMETERS WAS DETERMINED /6/ TO
REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY
PHILLIPS AND HOWE /7/.
IN THE STATISTICAL MODEL CALCULATION, COMPETING PROCESSES
OF FISSION, (N,2N), (N,3N) AND (N,4N), AND LEVEL
FLUCTUATION WERE CONSIDERED. THE LEVEL SCHEME OF CM-249
WAS TAKEN FROM REF./8/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0 1/2 +
1 26.22 3/2 +
2 42.4 5/2 +
3 52.18 7/2 +
4 110 9/2 +
5 110.1 7/2 +
6 146 9/2 +
7 208 3/2 +
CONTINUUM LEVELS ASSUMED ABOVE 220 KEV.
THE LEVEL DENSITY PARAMETERS : GILBERT AND CAMERON /9/.
GAMMA-RAY STRENGTH FUNCTION OF 4.8E-4 DEDUCED FROM
UNRESOLVED RESONANCE PARAMETERS.
MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS
CALCULATED WITH EVAPORATION MODEL/10/.
MT=18 FISSION
ESTIMATED AS 0.95 * SIG-F(CM-247) BY USING SYSTEMATICS OF
BEHRENS AND HOWERTON /11/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-57 CALCULATED WITH OPTICAL MODEL.
MT=16,17,18,37,91 ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,37,91 EVAPORATION SPECTRUM.
MT=18 MAXWELLIAN FISSION SPECTRUM.
TEMPERATURE ESTIMATED FROM SYSTEMATICS OF
SMITH ET AL./12/.
REFERENCES
1) KIKUCHI Y. AND NAKAGAWA T.: JAERI-M 84-116 (1984).
2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).
3) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438(1977).
4) DIAMOND H. ET AL.: ANL-7330 (1967).
5) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
6) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).
7) PHILLIPS T.W. AND HOWE F.R.: NUCL. SCI. ENG., 69, 375 (1979).
8) LEDERER C.M. AND SHIRLEY V.S.: TABLE OF ISOTOPES , 7TH ED.
(1978).
9) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446(1965).
10) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965).
11) BEHRENS J.W. AND HOWERTON R.J.: NUCL. SCI. ENG., 65,464(1978).
12) SMITH A.B. ET AL.: ANL/NDM-50 (1979).