96-Cm-243
96-CM-243 JAERI EVAL-MAR89 T.NAKAGAWA
DIST-SEP89
----JENDL-3.2 MATERIAL 9634
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
81-03 EVALUATION FOR JENDL-2 WAS MADE BY T.NAKAGAWA AND S.IGARASI
(JAERI) /1/.
89-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA (JAERI)/2/.
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 /3/.
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
BASED ON THE EXPERIMENTAL DATA AT THERMAL ENERGY BY JAFFEY
AND LERNER /4/, AND ZHURAVLEV ET AL. /5/, AND ON THE
EMPIRICAL FORMULA BY HOWERTON /6/.
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCE REGION (SLBW): 1.0E-5 EV TO 70 EV.
RESONANCE ENERGIES = ANUFRIEV ET AL. /7/
NEUTRON WIDTHS = ANUFRIEV ET AL. /7/ (ASSUMING 2G=1)
RADIATIVE WIDTHS = 0.040 EV (ASSUMED)
FISSION WIDTHS = TOTAL WIDTH /7/ - (WN+WG)
SCATTERING RADIUS = 10 FM.
A NEGATIVE RESONANCE WAS ADOPTED SO AS TO REPRODUCE WELL
THE THERMAL CROSS SECTIONS/8/.
UNRESOLVED RESONANCE PARAMETERS : 70 EV - 40 KEV
PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/ SO
AS TO REPRODUCE THE FISSION CROSS SECTION BASED ON SILBERT
/10/, AND THE TOTAL CROSS SECTION CALCULATED WITH OPTICAL
MODEL.
ENERGY INDEPENDENT PARAMETERS:
R=9.810 FM, S2=1.70E-4, WG=0.04 EV, WF=1.481 EV
ENERGY DEPENDENT PARAMETERS AT 1 KEV:
S0=1.32E-4, S1=1.06E-4, D=0.799 EV.
CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.
2200 M/SEC RES. INTEG.
TOTAL 757.5 B -
ELASTIC 9.926 B -
FISSION 617.4 B 1560 B
CAPTURE 130.2 B 199 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 40 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE
PARAMETERS.
MT=1,2,4,51-63,91,102,251 TOTAL, ELASTIC AND INELASTIC
SCATTERING, CAPTURE CROSS SECTIONS AND MU-L
CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE
CASTHY/11/.
THE SPHERICAL OPTICAL POTENTIAL PARAMETERS (MEV,FM):
V =41.0-0.107*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 /12/ TO
REPRODUCE WELL THE TOTAL CROSS SECTION OF AM-241 BY
PHILLIPS AND HOWE /13/, AND A REAL PART WAS MODIFIED A
LITTLE TO GIVE A SLIGHTLY LARGE STRENGTH FUNCTION IN A LOW
ENERGY REGION.
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-243
WAS TAKEN FROM THE COMPILATION BY ELLIS-AKOVALI /14/:
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 5/2 +
1 0.042 7/2 +
2 0.0874 1/2 +
3 0.094 9/2 +
4 0.094 3/2 +
5 0.133 7/2 +
6 0.153 11/2 +
7 0.164 9/2 +
8 0.219 13/2 +
9 0.228 11/2 +
10 0.260 9/2 +
11 0.530 15/2 -
12 0.729 1/2 -
13 0.769 3/2 -
OVERLAPPING LEVELS ARE ASSUMED ABOVE 0.82 MEV. THE LEVEL
DENSITY PARAMETERS WERE DETERMINED ON THE BASIS OF NUMBERS
OF EXCITED LEVELS/15/ AND RESONANCE LEVEL SPACING/8/.
CM-244 CM-243
A(1/MEV) 28.0 28.0
T(MEV) 0.395 0.40
C(1/MEV) 1.8807 7.5405
E-X(MEV) 4.2893 3.8863
SPIN-CUTOFF(1/MEV**0.5) 30.17 30.08
PAIRING E(MEV) 1.22 0.72
AVERAGE RADIATIVE WIDTH = 0.040 EV AND D = 0.809 EV /7/
WERE USED FOR THE CAPTURE CROSS SECTION CALCULATION.
MT=16,17,37 (N,2N),(N,3N) AND (N,4N) CROSS SECTIONS
CALCULATED WITH THE EVAPORATION MODEL BY PEARLSTEIN/16/.
NEUTRON EMISSION CROSS SECTION WAS ASSUMED TO BE (COMPOUND
NUCLEUS FORMATION CROSS SECTION CALCULATED WITH OPTICAL
MODEL - FISSION).
MT=18 FISSION CROSS SECTION
BELOW 10 KEV : TAKEN FROM JENDL-2 EVALUATION BASED ON
SILBERT /10/.
10 KEV - 3 MEV: DETERMINED FROM FOMUSHKIN ET AL. /17/.
ABOVE 3 MEV : ESTIMATED.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-63,91
LEGENDRE COEFFICIENTS CALCULATED WITH CASTHY /11/.
MT=16,17,18,37
ISOTROPIC DISTRIBUTIONS IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,37,91 EVAPORATION SPECTRUM.
MT=18 FISSION SPECTRUM ESTIMATED FROM Z**2/A SYSTEMATICS BY
SMITH ET AL. /18/ BY ASSUMING E(CF-252) = 2.13 MEV.
REFERENCES
1) NAKAGAWA T. AND IGARASI S.: JAERI-M 9601 (1981).
2) NAKAGAWA T.: TO BE PUBLISHED AS JAERI-M REPORT.
3) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).
4) JAFFEY A.H. AND LERNER J.L.: NUCL. PHYS., A145, 1, (1970).
5) ZHURAVLEV K.D. ET AL. : PROC. 2ND NAT. SOVIET CONF. ON NEUT.
PHYS., VOL.4, 57 (1974).
6) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
7) ANUFRIEV V.A. ET AL.: SOV. AT. ENERGY, 51, 736 (1982).
8) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, PART B",
ACADEMIC PRESS (1984).
9) KIKUCHI Y.: PRIVATE COMMUNICATION.
10) SILBERT M.G.: LA-6239 (1976).
11) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).
12) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).
13) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG. 69, 375 (1979).
14) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 44, 407 (1985).
15) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE, AS OF JAN. 1989.
16) PEARLSTEIN S.: J. NUCL. ENERGY 27, 81 (1973).
17) FOMUSHKIN E.F. ET AL.: SOV. AT. ENERGY, 62, 337 (1987).
18) A.B. SMITH ET AL. : ANL/NDM-50 (1979).