96-Cm-242
96-CM-242 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU
DIST-MAR02 REV2-DEC00 20001212
----JENDL-3.3 MATERIAL 9631
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
79-03 EVALUATION FOR JENDL-2 WAS MADE BY S.IGARASI AND T.NAKAGAWA
(JAERI) /1/.
89-03 RE-EVALUATION FOR JENDL-3 WAS MADE BY T.NAKAGAWA(JAERI)/2/
95-10 NEW EVALUATION FOR JENDL ACTINIDE FILE WAS MADE BY
T.NAKAGAWA AND T.LIU.
00-08 MODIFICATION WAS MADE BY T.NAKAGAWA.
***** Modified parts from JENDL-3.2 *******************
(1,455)
MF=2 Unresolved resonance parameters
MF=3 All data except (3,18)
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 /3/.
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
SEMI-EMPIRICAL FORMULA BY HOWERTON /4/.
MF=2,MT=151 RESONANCE PARAMETERS
ALL PARAMETERS WERE TAKEN FROM JENDL-3.2.
RESOLVED RESONANCE REGION : 1.0E-5 EV TO 275 EV.
RESONANCE ENERGIES = ARTAMONOV ET AL. /5/,
NEUTRON WIDTHS = ARTAMONOV 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 - 30 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 30 KEV AND
CAPTURE CROSS SECTIONS FROM 6 TO 30 KEV CALCULATED WITH
CASTHY /9/.
CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.
2200 M/SEC RES. INTEG.
TOTAL 32.57 B ---
ELASTIC 11.61 B ---
FISSION 5.06 B 19.9 B
CAPTURE 15.90 B 107 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 30 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE
PARAMETERS.
MT=1 TOTAL CROSS SECTION
CALCULATED WITH CASTHY CODE /9/ BASED ON THE SHERICAL
OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./10/ 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 /11/ WERE USED.
ISOTOPE CM-242 CM-243
A(1/MEV) 28.0 28.0
SPIN-CUTOFF PARA. 30.00 30.08
PAIRING E(MEV) 1.15 0.72
TEMP.(MEV) 0.4 0.4
C(1/MEV) 2.5771 7.5405
EX(MEV) 4.3163 3.8863
THE LEVEL SCHEME TAKEN FROM REF./12/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0 0 +
1 42.1 2 +
2 138.0 4 +
3 284.0 6 +
CONTINUUM LEVELS ASSUMED ABOVE 310 KEV.
MT= 2 ELASTIC SCATTERING
CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.
MT= 4 TOTAL INELASTIC SCATTERING
SUM OF MT=51, 52, 53 AND 91.
MT=16,17 (N,2N),(N,3N) CROSS SECTION
STAPRE RESULTS CALCULATED BY KONSHIN /13/ WERE ADOPTED.
MT=18 FISSION CROSS SECTION
(TAKEN FROM JENDL-3.2)
BELOW 1 MEV, CROSS SECTION WAS DETERMINED ON THE BASIS OF
DATA MEASURED BY ALAM ET AL./6/ AND VOROTNIKOV ET AL.
/14/ ABOVE 1 MEV, JENDL-2 EVALUATION WAS ADOPTED, WHICH
WAS BASED ON THE SHAPE OF CM-244 /15/ AND THE EMPIRICAL
FORMULA ON THE FISSION-CROSS-SECTION SYSTEMATICS AROUND 4
MEV BY BEHRENS AND HOWERTON /16/.
MT=51,52,53 INELASTIC SCATTERING
CALCULATED WITH ECIS /17/ AND CASTHY /9/ CODES.
CH.LAGRANGE'S DEFORMED OPTICAL POTENTIAL PARAMETERS /18/
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=91 CONTINUUM INELASTIC SCATTERING
CALCULATED WITH CASTHY CODE /9/. CROSS SECTIONS OF MT=91
ABOVE 10 MEV WERE MODIFIED TO A SMOOTH CURVE.
MT=102 RADIATIVE CAPTURE
CALCULATED WITH CASTHY/9/. AVERAGE LEVEL SAPCING OF 18 EV
AND CAPTURE WIDTH OF 0.04 EV WERE ASSUMED. DIRECT AND
SEMI-DIRECT CAPTURE CROSS SECTIONS WERE ESTIMATED WITH DSD
CODE /19/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
BELOW 300 KEV: CALCULATED WITH CASTHY CODE /9/
ABOVE 500 KEV: CALCULATED WITH ECIS CODE /17/
MT=16,17,18
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MT=51,52,53
SUM OF ECIS AND CASTHY CALCULATIONS.
MT=91
CALCULATED WITH CASTHY CODE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
CALCULATED WITH EGNASH /20/.
MT=18
MAXWELLIAN FISSION SPECTRUM WITH TEMPERATURE ESTIMATED FROM
SYSTEMATICS OF HOWERTON AND DOYAS /21/. THE RATIOS OF
MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM STAPRE
CALCULATION/13/.
REFERENCES
1) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).
2) NAKAGAWA T.: JAERI-M 90-101 (1990).
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. ET AL.: JAERI-DATA/CODE 99-025 (1999).
9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
10) IGNATYUK A.V. ET AL.: SOV. J. NUCL. PHYS., 42, 360 (1985).
11) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
12) SHURSHIKOV E.N. ET AL.: NUCL. DATA SHEETS, 45, 509 (1985).
13) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).
14) VOROTNIKOV P.E. ET AL.: SOV. J. NUCL. PHYS., 40, 726 (1984).
15) IGARASI S. AND NAKAGAWA T.: JAERI-M 7175 (1977).
16) BEHRENS J.W. AND HOWERTON R.J.: NUCL. SCI. ENG., 65, 464
(1978).
17) RAYNAL J.: IAEA SMR-9/8 (1970).
18) LAGRANGE CH. AND JARY J.: NEANDC(E) 198 "L" (1978).
19) KAWANO T.: PRIVATE COMMUNICATION (1999).
20) YAMAMURO. N.: JAERI-M 90-006 (1990).
21) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414
(1971).