96-CM-249 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU
DIST-MAR02 REV3-DEC00 20001213
----JENDL-3.3 MATERIAL 9652
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
84-03 EVALUATION FOR JENDL-3 WAS MADE BY Y.KIKUCHI AND
T.NAKAGAWA (JAERI) /1/.
92-09 JENDL-3.2
COMPILED BY T.NAKAGAWA
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY
T.NAKAGAWA AND T.LIU.
00-04 MODIFICATION WAS MADE AND COMPILED BY T.NAKAGAWA
***** Modified parts from JENDL-3.2 *******************
ALL DATA OF MF'S= 2, 3, 4 AND 5
*******************************************************
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 /2/.
MT=456 Number of prompt neutrons per fission
SEMI-EMPIRICAL FORMULA BY HOWERTON /3/.
MF=2,MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCES FOR SLBW FORMULA : 1.0E-5 EV TO 150 EV
HYPOTHETICAL RESONANCE LEVELS WERE GENERATED, AND THEIR
PARAMETERS WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS
Level spacing = 20.0 eV, capture width = 0.04 eV,
S-0 = 1.0E-4, R = 9.23 FM. ratio of neutron and
fission width = 0.4
PARAMETERS OF THE FIRST POSITIVE LEVEL WERE ADJUSTED SO AS TO
REPRODUCE THE THERMAL CROSS SECTIONS.
Capture (Maxwell av.) = 1.6 b /4/
Fission = about 10 b estimated from
systematics.
UNRESOLVED RESONANCES (150 EV TO 25 KEV)
D-0=20 EV, RADIATIVE WIDTH = 0.0400 EV,
Fission width = energy dependent parameters obtained with
ASREP code /5/ so as to reproduce estimated fission cross
section.
Neutron strength functions = adjusted with ASREP /5/ to
toatl and capture cross sections calculated with CASTHY
code /6/.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 20.75 B -
ELASTIC 8.76 B -
FISSION 10.23 B 166 B
CAPTURE 1.76 B 62.2 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
CALCULATED WITH CASTHY CODE /6/ BASED ON THE SHERICAL
OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./7/ WERE
USED.
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)
COMPETING PROCESSES OF THE FISSION, (N,2N) AND (N,3N) WERE
TAKEN INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS
OF GILBERT-CAMERON'S FORMULA /8/ WERE USED.
ISOTOPE CM-249 CM-250
A(1/MEV) 32.0 30.00
SPIN-CUTOFF PARA. 32.69 31.74
PAIRING E(MEV) 0.720 1.585
TEMP. (MEV) 0.370 0.400
C(1/MEV) 11.680 1.635
EX(MEV) 3.8937 5.0821
THE LEVEL SCHEME TAKEN FROM REF. /9/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0.0 1/2 +
1. 26.234 3/2 +
2. 48.203 5/2 +
3. 48.743 7/2 +
4. 109.0 9/2 +
5. 110.16 7/2 +
6. 146.0 9/2 +
7. 207.99 3/2 +
8. 220.0 9/2 +
9. 242.01 5/2 +
10. 288.99 7/2 +
11. 300.0 11/2 +
12. 350.0 9/2 +
13. 470.21 3/2 -
14. 494.49 1/2 -
15. 498.0 7/2 -
16. 529.61 5/2 +
17. 546.86 5/2 -
18. 578.43 7/2 +
19. 634.0 9/2 +
CONTINUUM LEVELS ASSUMED ABOVE 688 KEV.
MT= 2 ELASTIC SCATTERING
CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.
MT= 4 TOTAL INELASTIC SCATTERING
SUM OF MT=51 to 69 AND 91.
MT=16,17 (N,2N) and (N,3N)
STAPRE RESULTS CALCULATED BY KONSHIN /10/ were adopted.
MT=18 FISSION CROSS SECTION
Above 250 keV, Konshin's calculation/10/ was adopted.
Below 250 keV, roughly estimated to connect to the
average cross section the resolved resonance region.
MT=51, 52, 53, 54 Inelastic scattering
CALCULATED WITH ECIS /11/ AND CASTHY /6/ CODES.
LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /12/ WERE
USED for the ECIS calculation.
V = 49.82 - 17*((N-Z)/A) - 0.3*EN (MEV)
WS = 5.52 - 9*((N-Z)/A)+ 0.4*EN (MEV) EN=< 10 MEV
= 9.52 - 9*((N-Z)/A) (MEV) 10 =