96-Cm-240 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9625
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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** Original data taken from: JEFF-3.1 **
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***************************** JEFF-3.1 *************************
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** Original data taken from: JENDL-3.3 **
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HISTORY
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY
T.NAKAGAWA AND T.LIU.
00-01 RECOMPILED BY T.NAKAGAWA
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT=455 AND MT=456
MT=455 DELAYED NEUTRON DATA
ESTIMATED FROM THE SYSTEMATICS BY TUTTLE /1/.
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
BASED ON THE EMPIRICAL FORMULA BY HOWERTON /2/.
MF=2 RESONANCE PARAMETERS
MT=151
RESOLVED RESONANCE PARAMETERS (MLBW, UP TO 150 EV)
SINCE NO EXPETIMENTAL DATA WERE AVAILAVBLE, HYPOTHETICAL
RESONANCE PARAMETERS WERE GENERATED.
ASSUMED PARAMETERS: S0 = 1.0E-4, D-OBS = 6.7775 EV
G-GAMMA = 0.036 EV, G-FISS = 0.002 EV,
R = 9.42 FM
UNRESOLVED RESONANCE PARAMETERS (UP TO 30 KEV)
D-OBS AND R WERE ADJUSTED TO TOTAL AND CAPTURE CROSS
SECTIONS CALCULATED WITH CASTHY CODE /3/.
ASSUMED PARAMETERS: S0 = 1.0E-4, S1 = 3.0E-4,
G-GAMMA = 0.036 EV, G-FISS = 0.002 EV
CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.
2200 M/SEC RES. INTEG.
TOTAL 198.4 B ---
ELASTIC 13.1 B ---
FISSION 9.8 B 44.6 B
CAPTURE 175.6 B 668 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 30 KEV: RESONANCE REGION.
ABOVE 30 KEV:
MT=1 TOTAL CROSS SECTION
CASTHY /3/ CALCULATION WAS ADOPTED.
CASTHY CALCULATION
------------------
SHERICAL OPTICAL POTENTIAL PARAMETERS /4/
V = 45.036-0.3*EN (MEV)
WS= 4.115+0.4*EN (MEV)
WV= 0 , VSO = 7.5 (MEV)
R = RSO = 1.256 , RS = 1.260 (FM)
A = ASO = 0.626 , B = 0.555+0.0045*EN (FM)
STATISTICAL MODEL CALCULATION WITH CASTHY CODE WAS MADE
CONSIDERING COMPETING PROCESSES OF FISSION, (N,2N),
(N,3N).
THE LEVEL DENSITY PARAMETERS OF GILBERT-CAMERON'S FORMULA
/5/
ISOTOPE CM-240 CM-241
A(1/MEV) 27.0 28.57
SPIN-CUTOFF PARA. 29.30 30.22
PAIRING E(MEV) 1.21 0.72
TEMP. (MEV) 0.4 0.378
C(1/MEV) 1.621 5.287
EX(MEV) 4.2 3.56
THE LEVEL SCHEME TAKEN FROM REF. /6/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0 0 +
1 38.0 2 +
CONTINUUM LEVELS ASSUMED ABOVE 60 KEV.
MT= 2 ELASTIC SCATTERING
CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.
MT= 4 TOTAL INELASTIC SCATTERING
SUM OF MT=51 AND MT=91.
MT=16,17,18 (N,2N), (N,3N) AND FISSION CROSS SECTION
STAPRE RESULTS CALCULATED BY KONSHIN /7/ WERE ADOPTED.
FISSION CROSS SECTION IN THE ENERGY RANGE FROM 30 TO 500
KEV WAS SMOOTHLY CONECTED TO THAT OF THE UNRESOLVED
RESONANCE REGION.
MT=51, 91 PARTIAL INELASTIC SCATTERING
CALCULATED WITH CASTHY CODE /3/.
MT=102 RADIATIVE CAPTURE
CALCULATED WITH CASTHY CODE/3/.
AVERAGE RADIATIVE WIDTH = 0.0358 EV AND D = 6.7775 EV
OBTAINED FROM SYSTEMATICS /8/ AND LEVEL DENSITY
PARAMETERS WERE USED.
DIRECT AND SEMI-DIRECT CAPTURE CROSS SECTIONS WERE
ESTIMATED WITH DSD CODE /9/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51,91
CALCULATED WITH CASTHY CODE /3/.
MT=16,17,18
ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
CALCULATED WITH EGNASH CODE /10/.
MT=18
MAXWELLIAN FISSION SPECTRUM. TEMPAREATURE WAS ESTIMATED
FROM SYSTEMATICS OF HOWERTON AND DOYAS /11/. THE RATIOS
OF MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM
STAPRE CALCULATION/7/.
REFERENCES
1) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979).
2) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
3) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
4) IGNATYUK A.V. ET AL. : SOV. J. NUCL. PHYS. 42(3) SEP. (1985).
5) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
6) TULI J.K.: NUCLEAR DATA SHEETS VOL 59, NUMBER 2 (1990).
7) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).
8) MALECKI H. ET AL.: YAD. FIZ., 37, 284 (1983).
9) KAWANO T.: PRIVATE COMMUNICATION (1999).
10) YAMAMURO. N.: JAERI-M 90-006 (1990).
11) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414
(1971).
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