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96-Cm-242 NEA RCOM-JUN82 E.MENAPACE
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9631
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
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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-SEP89)
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.
Total, delayed and prompt neutron data multiplicities,
and photon production data were taken from ENDF/B-VI
Components of the energy released by fission (MT=458)
updated by O. Serot et al. (JEF/DOC-887).
Fission Q updated consistently.
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, 3/102
All the threshold reactions are from JEF-2.2, i.e
3/4, 3/16, 3/17, 3/20, 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. Fission
spectrum in JEF-2.2 is energy dependent while it isn't in
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 ENERGY LIMITS IN MF=5
CORRECTED.
28-DEC-84: ENERGY REGIONS EXTENDED TO 20 MEV.
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-242 NEUTRON CROSS SECTION EVALUATION
EVALUATION IS DESCRIBED IN THE REPORT INDC(ITY)-7 (1982)
Relevent description extracted from the two evaluations
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA
MT=452 NUBAR THERMAL VALUE COMPUTED FROM SEMI-EMPIRICAL WORK
OF GORDEEVA AND SMIRENKIN(REF.1) AS REVISED BY MANERO AND
KONSHIN(REF.2). ENERGY DEPENDENCE BASED ON HOWERTON (REF. 3)
MT=455 DEL. NUBAR, M.C.BRADY AND T.R.ENGLAND, NSE 103,129(1989)
MT=458 ENERGY OF FISSION. SYSTEMATICS OF SHER
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCE REGION : 1.0E-5 EV TO 275 EV.
RESONANCE ENERGIES = ALTAMONOV ET AL. /5/,
NEUTRON WIDTHS = ALTAMONOV ET AL. /5/,
RADIATIVE WIDTHS = 0.040 EV,
FISSION WIDTHS = ALAM ET AL. /6/ FOR THE LOW-LYING 4
LEVELS, AND THE AVERAGE VALUE OF 0.004 EV
FOR OTHER LEVELS.
SCATTERING RADIUS = 9.38 FM.
A NEGATIVE RESONANCE WAS ADDED AT -3.45 EV, AND ITS
PARAMETERS WERE ADJUSTED SO AS TO REPRODUCE WELL THE
THERMAL CROSS SECTIONS/7/. BACKGROUND CROSS SECTION WAS
GIVEN TO THE FISSION CROSS SECTION.
UNRESOLVED RESONANCE PARAMETERS : 275 EV - 40 KEV
PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP /8/
SO AS TO REPRODUCE THE FISSION CROSS SECTION MEASURED BY
ALAM ET AL./6/, AND TOTAL CROSS SECTION AT 40 KEV.
ENERGY INDEPENDENT PARAMETERS:
R=9.093 FM, S0=0.92E-4, S2=0.97E-4, WG=0.04 EV.
ENERGY DEPENDENT PARAMETERS AT 1 KEV:
S1=3.04E-4, WF=0.093 EV, D=17.16 EV.
CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.
2200 M/SEC RES. INTEG.
TOTAL 32.57 B ---
ELASTIC 11.61 B ---
FISSION 5.064 B 20.0 B
CAPTURE 15.90 B 109 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 40 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE
PARAMETERS.
MT=18,19 A 1/V COMPONENT IS GIVEN AT LOW ENERGIES
MT=251 MU-L CALCULATED WITH OPTICAL AND STATISTICAL MODEL
CODE CASTHY/9/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 LEGENDRE COEFFICIENTS CALCULATED WITH THE OPTICAL AND
STATISTICAL MODELS WERE GIVEN.
MT 51,52,53 LEGENDRE COEFFICIENTS COMPUTED BY SYSMF FROM JUPITOR
BY ADDING ISOTROPIC STATISTICAL CONTRIBUTION
MT 16,54 TO 79 AND 91 ASSUMED ISOTROPIC IN THE LABORATORY SYST.
MT 18,19,20 ASSUMED ISOTROPIC IN THE LABORATORY SYSTEM
MT=16,17,18 ISOTROPIC DISTRIBUTIONS IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT 16 EVAPORATION SPECTRUM(LF=9) ASSUMED, WITH T=T(E)GIVEN SE-
PARATELY FOR EACH NEUTRON
MT=17 EVAPORATION SPECTRUM.
MT 18,19 SIMPLE FISSION SPECTRUM,MAXWELLINA(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 Of THE JENDL-3.2 evaluation
1) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).
2) NAKAGAWA T.: TO BE PUBLISHED AS JAERI-M REPORT.
3) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).
4) HOWERTON R.J.: NUCL. SCI. ENG. 62, 438 (1977).
5) ARTAMONOV V.S. ET AL. : PROC. OF 4TH ALL UNION CONF. ON
NEUTRON PHYSICS, KIEV (1977), VOL. 2, 257.
6) ALAM B. ET AL.: NUCL. SCI. ENG., 99, 267 (1988).
7) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL. 1, PART B",
ACADEMIC PRESS (1984).
8) KIKUCHI Y.: PRIVATE COMMUNICATION.
9) IGARASI S.: J. NUCL. SCI. TECHNOL., 12, 67 (1975).
10) PHILLIPS T.W. AND HOWE R.E.: NUCL. SCI. ENG. 69, 375 (1979).
11) ENSDF, EVALUATED NUCLEAR STRUCTURE DATA FILE, AS OF JAN. 1989.
12) PEARLSTEIN S.: J. NUCL. ENERGY 27, 81 (1973).
13) VOROTNIKOV P.E. ET AL.: SOV. J. NUCL. PHYS., 40, 726 (1984).
14) IGARASI S. AND NAKAGAWA T.: JAERI-M 7175 (1977).
15) BEHRENS J.W. AND HOWERTON R.J.: NUCL. SCI. ENG., 65, 464
(1978).
16) SMITH A.B. ET AL.: ANL/NDM-50 (1979).
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