96-CM-247 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU
JAERI-RESEARCH 97-056 DIST-MAR02 REV2-OCT00 20001003
----JENDL-3.3 MATERIAL 9646
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
83-03 EVALUATION WAS BY Y.KIKUCHI(JAERI)/1/.
89-03 RE-EVALUATION WAS MADE FOR JENDL-3 BY T.NAKAGAWA(JAERI)/2/
95-10 NEW EVALUATION WAS MADE BY T.NAKAGAWA AND T.LIU/3/.
99-12 RECOMPILED BY T.NAKAGAWA.
THE FOLLOWING QUANTITIES ARE RE-EVALUATED AFTER JAERI-
RESEARCH 97-056:
MF=2 MT=151
MF=3 MT=102 DIRECT/SEMI-DIRECT MODIFIED.
MT=37 DELETED
MF=4 MT= 2 BELOW 600 KEV, REPLACED WITH CASTHY CALC.
MF=5 MT=16, 17, 18, 91
***** Modified parts from JENDL-3.2 *******************
MF=2 All data
MF=3 All data
MF=4 All data
MF=5 All data
*******************************************************
MF=1 GENERAL INFORMATION
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 /4/.
MT=456 PROMPT NEUTRON DATA
SEMI-EMPIRICAL FORMULA BY HOWERTON /5/.
MF=2,MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCE REGION (SLBW) : 1.0E-5 TO 60 EV
EVALUATION WAS BASED ON THE EXPERIMENTAL DATA OF MOORE AND
KEYWORTH/6/, BELANOVA ET AL./7/ AND DANON ET AL./8/
PARAMETERS OF RESONANCES UP TO 21.2 EV WERE TAKEN FROM
DANON ET AL./8/ PARAMETERS OF -0.52-EV AND 1.23-EV
RESONANCES WERE ADJUSTED TO TO REPRODUCE THERMAL CROSS
SECTIONS AND RESONANCE INTEGRALS.
RADIATIVE WIDTHS = 0.040 EV WAS ASSUMED.
SCATTERING RADIUS = 9.14 FM.
UNRESOLVED RESONANCE REGION : 60 EV TO 30 KEV
PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/
SO AS TO REPRODUCE THE FISSION CROSS SECTION OF DANON
ET AL./8/, AND THE TOTAL AND CAPTURE CROSS SECTIONS AT
30 KEV CALCULATED WITH OPTICAL AND STATISTICAL MODELS.
ENERGY INDEPENDENT PARAMETERS:
R=8.76 FM, WG=0.035 EV,.
SPIN DEPENDENT FISSION WIDTHS WERE ASSUMED.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/SEC RES. INTEG.
TOTAL 176.1 B -
ELASTIC 7.95 B -
FISSION 111.3 B 1130 B
CAPTURE 56.9 B 574 B
THE THERMAL CROSS SECTION AND RESONANCE INTEGRAL OF FISSION
ARE IN GOOD AGREEMENT WITH 115+-8 B AND 1091+-80 B MEASURED
BY DANON ET AL./8/, RESPECTIVELY.
MF=3 NEUTRON CROSS SECTIONS
BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE
PARAMETERS.
MT=1 TOTAL CROSS SECTION
CASTHY /10/ CALCULATION WAS ADOPTED.
CASTHY CALCULATION
------------------
SHERICAL OPTICAL POTENTIAL PARAMETERS /11/
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
/12/
ISOTOPE CM-247 CM-248
A(1/MEV) 29.3 31.0
SPIN-CUTOFF PARA. 31.11 32.09
PAIRING E(MEV) 0.72 1.623
TEMP. (MEV) 0.408 0.385
C(1/MEV) 13.967 1.2545
EX(MEV) 4.2678 4.9631
THE LEVEL SCHEME TAKEN FROM REF. /13/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0.0 9/2 -
1 61.5 11/2 -
2 135.0 13/2 -
3 217.0 15/2 -
4 227.0 5/2 +
5 266.0 7/2 +
6 285.0 7/2 +
CONTINUUM LEVELS ASSUMED ABOVE 309 KEV.
MT=2 ELASTIC SCATTRING
CALCULATED AS (TOTAL - SUM OF PARTIAL CROSS SECTIONS).
MT= 4 TOTAL INELASTIC SCATTERING
SUM OF MT=51-91.
MT=16,17 (N,2N),(N,3N) CROSS SECTION
STAPRE RESULTS CALCULATED BY KONSHIN /14/ WERE ADOPTED.
MT=18 FISSION CROSS SECTION
EVALUATED ON THE BASIS OF THE MEASURED DATA BY DANON ET
AL./15/ BELOW 80 KEV. ABOVE THIS ENERGY, THE DATA OF
FOMUSHKIN ET AL./16/ WERE ADOPTED. FROM 11 MEV TO 20
MEV, THE FISSION CROSS SECTION OF JENDL-3.2 WAS SLIGHTLY
ADJUSTED ACCORDING TO THE NEW EXPERIMENTAL DATA OF
FOMUSHKIN ET AL./17/.
MT=51, 52, 53 INELASTIC SCATTERING
CALCULATED WITH ECIS /18/ AND CASTHY /10/ CODES.
IN THE ECIS CALCULATION, CH.LAGRANGE'S DEFORMED OPTICAL
POTENTIAL PARAMETERS /19/ WERE USED.
V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV)
WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) 0 =