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9.624400+4 2.419660+2 1 1 2 0
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 0 125 1
96-Cm-244 HEDL,SRL,+ EVAL-APR78 MANN,BENJAMIN,HOWERTON,ET AL.
HEDL TME 77-54 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 9637
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
Original data taken from: ENDF/B-VI.8
Components of the energy released by fission (MT=458)
updated by O. Serot et al. (JEF/DOC-887).
05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)
ENDF/B-V MATERIAL CONVERTED TO ENDF-6 FORMAT BY NNDC
* * * * * * *
HEDL EVAL-APR78 MANN AND SCHENTER (FAST)
SRL EVAL-JUL75 BENJAMIN (THERMAL)
LLL EVAL-APR78 HOWERTON (GAMMA PRODUCTION)
ANC+AI EVAL-MAY67 DUNFORD + ALTER
APR74 EXTENDED TO 20 MEV FOR ENDF/B
VERSION IV
MF=1 GENERAL INFORMATION (MT=452-456, JENDL3.3)
MT=451 COMMENTS AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT'S =455 AND 456.
MT=455 DELAYED NEUTRON DATA
SEMI-EMPIRICAL FORMULA BY TUTTLE (REF. 1)
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
SEMI-EMPIRICAL FORMULA BY HOWERTON (REF. 2-3)
MT=458 ENERGY FROM FISSION BASED ON SHER (REF. 17)
MF=2 RESONANCE PARAMETERS(0 EV TO 10 KEV)
MT=151 RESOLVED RESONANCES PARAMETERS ARE INCLUDED FOR 37 RE-
SOLVED RESONANCES AND ONE BOUND LEVEL BASED ON ORELA, LASL,
AND MTR MEASUREMENTS(REFS.4-6) UP TO 520 EV. PARAMETERS OF
THE BOUND LEVEL AND THE FIRST RESONANCE WERE MODIFIED WITHIN
REASONABLE EXPERIMENTAL LIMITS TO PROVIDE AGREEMENT WITH
INTEGRAL DATA (REFS. 7 + 8) AND PRODUCTION STUDIES (REFS.9 +
10). THE POTENTIAL SCATTERING CROSS SECTION IS 10.32 BARNS
FROM OPTICAL MODEL CALCULATIONS. 2200 M/S CROSS SECTIONS
FROM RESONANCE PARAMETERS ARE CAPTURE- 10.4 B, FISSION-
0.60 B, ELASTIC- 7.16 B, TOTAL- 18.13 B. THIS VALUE DIFFERS
FROM THE TOTAL CROSS SECTION DETERMINED BY BERRETH ET AL.
(23+-3 B), BUT BERRETH S DATA WAS NOT CORRECTED FOR SMALL
ANGLE SCATTERING, A CORRECTION WHICH WOULD REDUCE THE MEAS-
URED 2200 M/S TOTAL CROSS SECTION SIGNIFICANTLY. RESOLVED
RANGE- 0 TO 525 EV.
UNRESOLVED RESONANCES PARAMETERS FOR S-WAVE RESONANCES
ARE AVERAGES FROM THE RESOLVED REGION, WITH THE FISSION
WIDTH FROM MOORE S MORE EXTENSIVE DATA FOR THE FISSION RESO-
NANCES(REF. 5). FOR THE P-WAVE RESONANCES- D, GG, AND GF
ARE ALSO BASED ON THE RESOLVED REGION, WHILE GN0 IS DETERMIN-
ED FROM THE P-WAVE STRENGTH FUNCTIONS OF DUNFORD AND ALTER
(REF. 11). UNRESOLVED RANGE- 525 EV TO 10 KEV.
MF=3 SMOOTH CROSS SECTIONS(ABOVE 10 KEV)
MT=1 TOTAL CROSS SECTION FAST REGION FROM AN OPTICAL MODEL
CALCULATION (REF. 12).
MT=2 ELASTIC SCATTERING DATA OBTAINED IN PROCEDURE
IDENTICAL TO MT=1.
MT=4 INELASTIC SCATTERING DATA RESULTS FROM THE SCATTERING
TO 3 LEVELS PLUS CONTINUUM. AGAIN AN OM IS USED WITH A
STATISTICAL COMPOUND NUCLEUS MODEL (REF. 12)
MT=16 N,2N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 12)
MT=17 N,3N BASED ON STATISTICAL MODEL CALCULATIONS (REF. 12)
MT=18 FISSION THERMAL REGION DATA CALCULATED FROM RESONANCE
PARAMETERS. FAST REGION BASED ON DATA OF MOORE (REF 13),
WITH HIGHER ENERGY EVALUATIONS BASED ON STATISTICAL MODEL
CALCULATIONS (REF 12).
MT=19 (N,F) SAME AS MT=18 UNTIL (N,NF) THRESHOLD, CONSTANT
THEREAFTER.
MT=20 (N,NF) DIFFERENCE OF MT=18 AND MT=19
MT=51,52,53,91 INELASTIC SCATTERING DATA RESULTS FROM THE
SCATTERING TO 3 LEVELS PLUS CONTINUUM. AGAIN AN OM IS
USED WITH A STATISTICAL COMPOUND NUCLEUS MODEL (REF. 12)
MT=102 CAPTURE THERMAL DATA CALCULATED FROM RESONANCE
PARAMETERS. FAST REGION DATA FROM A STATISTICAL MODEL
ASSUMING DIPOLE RADIATION.
MF=4 LEGENDRE POLYNOMIALS
MT=2 ELASTIC SCATTERING LEGENDRE COEFFICINTS FOR 15TH
ORDER FIT TO CALCULATED ANGULAR DISTRIBUTIONS (DOM) ARE
PROVIDED BETWEEN 10 KEV AND 11 MEV AND 19TH ORDER BETWEEN
12 AND 15 MEV.
MT%2 ASSUMED ISOTROPIC
MF=5 SECONDARY ENERGY DISTRIBUTIONS
MT=16 N,2N NUCLEAR TEMPERATURE WITH ENERGY DEPENDENCE AS IN
REFERENCE 14.
MT=17 SAME REFERENCE AS MT=16
MT=18 FISSION MAXWELLIAN WITH CONSTANT TEMPERATURE FROM
CORRELATION OF REF. 15.
MT=19 AND 20 SAME AS MT=18
MT=91 BASED ON PARAMETERS OF GILBERT AND CAMERON (REF. 16)
REFERENCES
1. TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).
2. HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
3. R.J.HOWERTON,NUCL.SCI.ENG.46(1971)42.
4. O.SIMPSON,F.SIMPSON,T.YOUNG,J.HARVEY,N.HILL, + R.
BENJAMIN(PRIVATE COMMUNICATION)
5. M.MOORE + G.KEYWORTH,PHYS.REV.C3(1971)1656
6. J.BERRETH,F.SIMPSON, + B.RUSCHE,NUCL.SCI.ENG.49(1972)145
7. R.BENJAMIN,K.MACMURDO + J.SPENCER,NUCL.SCI.ENG.47(1972)203
8. M.THOMPSON,M.HYDER, + R.REULAND,J.INORG.NUCL.CHEM.33(1971)
1553
9. R.BENJAMIN,V.VANDERVELDE,T.GORRELL + F.MCCROSSON,PROC.CONF.
NUCL.CROSS SECT. + TECH.,WASH.,D.C.,MAR.,1975
10. R.BENJAMIN,V.VANDERVELDE,T.GORRELL + F.MCCROSSON,USERDA
REPORT TO BE ISSUED(WILL SUPERCEDE REF. 12)
11. C.DUNFORD + H.ALTER,USAEC REPORT NAA-SR-12271(1967)
12. F.M.MANN + R.E.SCHENTER, TRANS. AMER. NUC. SOC. 23(1976)546
AND HEDL TME 77-54 (1977)
13. M.S.MOORE AND G.A.KEYWORTH, PHYS. REV. C3(1971)1656
14. K.PARKER,AWREO-79/63(1964)
15. E.BARNARD ET AL.,NUCL.PHYS.71(1965)228
16. A. GILBERT AND A.G.W. CAMERON, CAN. J. PHYS. 43(1965)1466
17. R SHER AND C. BECK EPRI NP-1771 1981 AND REV.1 JAN. 1983
MF=12,13,14,15 PHOTON PRODUCTION
FILES TAKEN FROM THE LLL EVALUATIONS OF R. HOWERTON
DOCUMENTED IN UCRL 50400, VOL. 15, PART A (METHODS) SEPT 75
AND PART B (CURVES) APR 76. FILES EXTENDED TO THE ENERGY
RANGE 1.-5 EV TO 20 MEV AND MERGED TO THIS EVALUATION
AT BNL BY R. KINSEY.
1 451 130
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