96-CM-241 JAERI EVAL-JUN95 T.NAKAGAWA AND T.LIU
DIST-MAR02 REV2-DEC00 20001213
----JENDL-3.3 MATERIAL 9628
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
89-03 EVALUATION FOR JENDL-3 WAS MADE BY T. NAKAGAWA(JAERI)/1/.
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY
T.NAKAGAWA AND T.LIU.
00-02 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 MLBW FORMULA : 1.0E-5 EV TO 150 EV
HYPOTHETICAL RESONANCE LEVELS WERE GENERATED. THEIR PARAMETERS
WERE DETERMINED FROM THE ASSUMED AVERAGE PARAMETERS:
D-OBS = 1.8 EV, RADIATIVE CAPTURE WIDTH = 0.040 EV,
S-0 = 1.0E-4, FISSION WITH = 0.5 EV, R = 9.40 FM.
THE FIRST RESONANCE WAS ASSUMED AT (D-OBS)*0.5 EV. NO
NEGATIVE LEVELS WERE ASSUMED.
UNRESOLVED RESONANCES : 150 EV TO 30 KEV
S0 = 0.7E-4, S1 = 2.0E-4, D-OBS =1.8 EV AND RADIATIVE WIDTH =
0.04 EV WERE ASSUMED. THE FISSION WIDTH, AND S0 AND S1 WERE
DETERMINED WITH ASREP /4/ SO AS TO REPRODUCE ASSUMED
FISSION CROSS SECTIONS AND TOTAL AND CAPTURE CROSS SECTIONS
CALCULATED WITH CASTHY /5/. R (9.33 FM) WAS DETERMINED TO
REPRODCE THE TOTAL CROSS SECTION CALCULATED WITH CASTHY.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 601.79 B
ELASTIC 7.99 B
FISSION 549.82 B 1180 B
CAPTURE 43.99 B 96.0 B
MF=3 NEUTRON CROSS SECTIONS
----- ABOVE THE RESONANCE REGION ---
MT=1 TOTAL CROSS SECTION
CALCULATED WITH CASTHY CODE /5/ BASED ON THE SHERICAL
OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./6/ 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 /7/ WERE USED.
ISOTOPE CM-241 CM-242
A(1/MEV) 28.57 28.0
SPIN-CUTOFF PARA. 30.22 30.0
PAIRING E(MEV) 0.72 1.15
TEMP.(MEV) 0.378 0.4
C(1/MEV) 5.287 2.5771
EX(MEV) 3.560 4.3163
THE LEVEL SCHEME TAKEN FROM REF. /8/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0 1/2 +
1 53. 3/2 +
2 103. 5/2 +
3 157. 7/2 +
4 255. 9/2 +
CONTINUUM LEVELS ASSUMED ABOVE 280 KEV.
MT= 2 ELASTIC SCATTERING
CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.
MT= 4 TOTAL INELASTIC SCATTERING
SUM OF MT=51, 52, 53, 54 AND 91.
MT=16,17,18 (N,2N), (N,3N) AND FISSION
STAPRE RESULTS CALCULATED BY KONSHIN /9/ WERE ADOPTED.
FISSION CROSS SECTION BELOW 500 KEV WERE ESTIMATED FROM THE
REACTION CROSS SECTIONS AND BRANCHING RATIOS TO OBTAIN THE
SUITABLE CAPTURE CROSS SECTIONS.
MT=51,52,53 INELASTIC SCATTERING
CALCULATED WITH ECIS /10/ AND CASTHY /5/ CODES.
CH.LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /11/
WERE USED.
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 =< EN =< 20 MEV
VSO = 6.2 (MEV)
R = RS = 1.26 , RSO = 1.12 (FM)
A = 0.63, AS = 0.52 , ASO = 0.47 (FM)
BETA-2 = 0.204 , BETA-4 = 0.051
MT=54,91 INELASTIC SCATTERING
CALCULATED WITH CASTHY CODE /5/. CROSS SECTION OF MT=91 AT
20 MEV WAS MODIFIED TO A SMOOTH CURVE.
MT=102 RADIATIVE CAPTURE
CALCULATED WITH CASTHY CODE/5/. AVERAGE RADIATIVE WIDTH =
0.040 EV AND D = 1.8 EV OBTAINED FROM SYSTEMATICS AND THE
LEVEL DENSITY PARAMETERS WERE USED. DIRECT AND SEMI-DIRECT
CAPTURE CROSS SECTIONS WERE ESTIMATED WITH DSD CODE /12/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
BELOW 300 KEV: CALCULATED WITH CASTHY CODE /5/
ABOVE 500 KEV: CALCULATED WITH ECIS CODE /10/
MT=16,17,18
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MT=51,52,53
SUM OF ECIS AND CASTHY CALCULATIONS.
MT=54,91
CALCULATED WITH CASTHY CODE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
CALCULATED WITH EGNASH /13/.
MT=18
MAXWELLIAN FISSION SPECTRUM. TEMPERATURE ESTIMATED FROM
SYSTEMATICS OF HOWERTON AND DOYAS /14/. THE RATIOS OF
MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM STAPRE
CALCULATION/9/.
REFERENCES
1) NAKAGAWA T.: JAERI-M 90-101 (1990).
2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, 29 (1979).
3) HOWERTON R.J.: NUCL. SCI. ENG. 62, 438 (1977).
4) KIKUCHI Y., ET AL.: JAERI-DATA/CODE 99-025 (1999).
5) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
6) IGNATYUK A.V. ET AL.: SOV. J. NUCL. PHYS., 42, 360 (1985).
7) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
8) AKOVALI Y.A.: NUCL. DATA SHEETS, 72, 191 (1994).
9) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).
10) RAYNAL J.: IAEA SMR-9/8 (1970).
11) LAGRANGE CH. AND JARY J.: NEANDC(E) 198 "L" (1978).
12) KAWANO T.: PRIVATE COMMUNICATION (1999).
13) YAMAMURO. N.: JAERI-M 90-006 (1990).
YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).
14) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414
(1971).