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9.624300+4 2.409730+2 1 1 2 2
0.000000+0 1.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 172 1
96-Cm-243 JAERI EVAL-MAR89 T.NAKAGAWA
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 9634
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
JENDL-3.2 (DIST-SEP90 REV-SEP93)
ENDF/B-VI (DIST-FEB90)
Basically, JENDL-3.2 data were adopted below 40 keV (limit
of the UNRR) and JEF-2.2 adopted at higher energies.
Energy released by fission and photon production data were
taken from ENDF/B-VI
Details on the compilation are as follows:
Data originating from JENDL-3.2 solely are those of the
following MF/MTs: 1/452, 1/455, 1/456, 2/151, 3/251, 4/2
The following MF/MTs are combinations of JENDL-3.2
(up to 40 keV) and JEF-2.2
3/1, 3/2, 3/18, 3/19, 3/102
All the threshold reactions are from JEF-2.2, i.e
3/4, 3/16, 3/17, 3/51 through 3/62, 3/91.
The angular distributions of MT=2 was taken from
JENDL-3.2. JEF-2.2 angular distributions were adopted
for MF=51, 52 and 53. For other reactions the distribution
was assumed isotropic in both evaluations.
The secondary energy distributions were taken from JEF-2.2
for the following reactions: MT=16,18,19 and 20. Fission
spectrum in JEF-2.2 is energy dependent while it isn't in
JENDL-3.2.
For MT=37, the energy distribution was taken from JENDL-3.2.
Partial fissions deleted due to inconsistency with the total
******************************************************************
HISTORY of the two evaluations
---------- JENDL-3.2 ----------
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/.
---------- JEF-2.2 ----------
19-AUG-84: FISSION Q-VALUES AND MF=5 ENERGY LIMITS CORRECTED.
28-DEC-84: ENERGY REGIONS EXTENDED TO 20 MEV.
11-MAR-86: ONE VALUE AT 20 MEV IN MF=5,MT=16 CORRECTED
6-APR-88: THE SPIN OF L=0,RESONANCES HAVE BEEN RANDOMLY
ASSIGNED BY THE COMPUTER CODE RNDSPIN
1) Q-VALUES AND THRESHOLD ENERGIES WERE MODIFIED.
2) THE TOTAL AND TOTAL INELASTIC SCATTERING CROSS SECTIONS WERE
RE-CALCULATED FROM PARTIAL CROSS SECTIONS.
ENEA EVAL-MAR82 CNEN-CDC-BOLOGNA
CURIUM-243 NEUTRON CROSS SECTION EVALUATION
EVALUATION DESCRIBED IN CNEN REPORT RT/FI(81)23 (1981)
Relevent description extracted from the two evaluations
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 AND 102 AND MT 18, 19 -NO SMOOTH BACKGROUND
MT=251 MU-L CALCULATED WITH OPTICAL AND STATISTICAL MODEL
CODE CASTHY/9/.
MT=37 (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).
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 LEGENDRE COEFFICIENTS CALCULATED WITH CASTHY /11/.
MT=16,54 TO 62 AND 91-ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM
MT=51,52,53-LEGENDRE COEFF.COMPUTED BY SYSMF FROM JUPITOR AND
ADAPE HAVING ADDED ISOTROPIC STATISTICAL CONTRIBUTION
MT=17,18,19,20 and 37 ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT 16-EVAPORATION SPECTRUM (LF=9) ASSUMED, WITH T=T(E) GIVEN
SPERATELY FOR EACH EMITTED NEUTRON
MT 18,19-SIMPLE FISSION SPECTRUM, MAXWELLIAN (LF=7) ASSUMED,
WITH T=T(E) FROM SYSTEMATICS
MT 20-EVAPORATION SPECTRUM (LF=9),WITH T=T(E)
MT 91-EVAPORATION SPECTRUM (LF=9), WITH T=T(E)
----------------------------------------------------------------
COMPUTER CODES USED FOR THE JEF-2.2 EVALUATION
1)-CRESO RESONANCE REGION DATA
2)-HAUSER5 STATISTICAL MODEL IN CONTINUUM REGION CALCULATIONS
3)-JUPITOR ,ADAPE FOR SHAPE ELASTIC ,DIRECT INELASTIC
AND TOTAL CROSS SECTIONS
4)-JUPITOR,ADAPE FOR ANGULAR DISTRIBUTIONS
5)-SYSMF DATA HANDLING AND FILE GENERATION
6)DICTION,CHECKER4,SUMUP4 CONSISTENCY CHECK ON FINAL TAPE
REFERENCES FOR THE JENDL-3.2 evaluation
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).
1 451 177
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