96-CM-244 JAERI EVAL-OCT95 T.NAKAGAWA AND T.LIU
DIST-MAR02 REV2-OCT00 20001003
----JENDL-3.3 MATERIAL 9637
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
77-03 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 Modified and compiled by T.Nakagawa.
***** Modified parts from JENDL-3.2 *******************
MF=2 Only the scattering radius in the unresolved resonance
region was changed.
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 /3/.
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
SEMI-EMPIRICAL FORMULA BY HOWERTON /4/.
MF=2,MT=151 RESONANCE PARAMETERS
(TAKEN FROM JENDL-3.2 )
RESOLVED RESONANCE REGION (MLBW) : 1.0E-5 TO 1 KEV
ABOVE 20 EV, PARAMETERS BY MOORE AND KEYWORTH /5/ WERE
ADOPTED ASSUMING NEUTRON WIDTH OF 0.2 EV FOR 646.9, 759.7,
914.0 AND 971.5 EV LEVELS, AND BELOW 20 EV, EVALUATION BY
BENJAMIN ET AL. /6/. THE FISSION WIDTHS OF LOW-LYING 4
LEVELS WERE REPLACED WITH THOSE BY MAGUIRE ET AL. /7/.
RADIATIVE WIDTH = 0.037 EV (ASSUMED)
SCATTERING RADIUS = 11.2 FM (ADJUSTED TO 11.6 B
AT 0.0253 EV /8/.
A NEGATIVE RESONANCE AT -1.48 EV WAS ADOPTED AND ITS
PARAMETERS WERE ADJUSTED SO AS TO REPRODUCE WELL THE
THERMAL CROSS SECTIONS/8/.
UNRESOLVED RESONANCE PARAMETERS : 1 KEV - 40 KEV
PARAMETERS WERE DETERMINED WITH A FITTING CODE ASREP/9/ SO
AS TO REPRODUCE THE FISSION CROSS SECTION OF MAGUIRE ET AL.
/7/, AND THE TOTAL AND CAPTURE CROSS SECTIONS CALCULATED
WITH OPTICAL AND STATISTICAL MODELS.
ENERGY INDEPENDENT PARAMETERS:
R=9.0 FM, S0=0.9E-4, S2=0.92E-4, WG=0.04 EV.
ENERGY DEPENDENT PARAMETERS AT 1 KEV:
S1=3.06E-4, WF=0.00244 EV, D=11.98 EV.
CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.
2200 M/SEC RES. INTEG.
TOTAL 27.20 B -
ELASTIC 11.06 B -
FISSION 1.037 B 13.4 B
CAPTURE 15.10 B 660 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 40 KEV, CROSS SECTIONS WERE REPRESENTED WITH RESONANCE
PARAMETERS.
MT=1 TOTAL CROSS SECTION
CALCULATED WITH CASTHY CODE /10/ BASED ON THE SHERICAL
OPTICAL MODEL. THE OPTICAL POTENTIAL OF REF./11/ 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 FISSION, (N,2N) AND (N,3N) WERE TAKEN
INTO ACCOUNT. THE FOLLOWING LEVEL DENSITY PARAMETERS OF
GILBERT AND CAMERON'S FORMULA /12/ WERE USED.
ISOTOPE CM-244 CM-245
A(1/MEV) 28.0 30.0
SPIN-CUTOFF PARA. 30.17 31.31
PAIRING E(MEV) 1.22 0.72
TEMP.(MEV) 0.395 0.391
C(1/MEV) 1.8807 11.288
EX(MEV) 4.2893 4.0295
THE LEVEL SCHEME TAKEN FROM REF. /13/.
NO. ENERGY(KEV) SPIN-PARITY
G.S. 0 0 +
1. 43.0 2 +
2. 142.4 4 +
3. 296.2 6 +
4. 501.8 8 +
5. 970.0 2 +
6. 984.9 0 +
7. 1020.8 2 +
8. 1038.0 2 +
9. 1040.2 6 +
CONTINUUM LEVELS ASSUMED ABOVE 1084.2 KEV.
MT= 2 ELASTIC SCATTERING
CALCULATED AS TOTAL - PARTIAL CROSS SECTIONS.
MT= 4 TOTAL INELASTIC SCATTERING
SUM OF MT=51 TO 59 AND 91.
MT=16,17 (N,2N), (N,3N) CROSS SECTIONS
STAPRE RESULTS CALCULATED BY KONSHIN /14/ WERE ADOPTED.
MT=18 FISSION CROSS SECTION
BELOW 100 KEV: SMOOTH CURVE BASED ON MAGUIRE ET AL. /7/.
100 - 800 KEV: JENDL-2 WAS ADOPTED, WHICH WAS OBTAINED BY
FITTING A SEMI-EMPIRICAL FORMULA TO THE
EXPERIMENTAL DATA OF REF. /5/.
0.8 - 6 MEV: ESTIMATED FROM EXPERIMENTAL DATA /5, 15,
16/.
6 -12 MEV: THE STAPRE RESULT CALCULATED BY KONSHIN /14/
WERE USED.
12 - 20 MEV: BY EYE GUIDE. LARGER VALUES THAN JENDL-3.2
WERE ADOPTED BASED ON THE MEASURED DATA OF
FOMUSHKIN ET AL. /17/
NOTE: THE RECENT EXPERIMENTAL DATA BY FURSOV ET AL./18/
WERE ALSO CONSIDERED. HOWEVER THEY WERE NOT ADOPTED BECAUSE
THEY SEEMED TO BE TOO LARGE.
MT=51, 52, 53, 54
THE SUM OF COMPOUND AND DIRECT PROCESSES.
THE RESULTS OF CASTHY CALCULATION WERE ADOPTED AS THE
COMPOUND CROSS SECTIONS. THE DIRECT ONES WERE CALCULATED
WITH ECIS CODE /19/ USING THE DEFORMED OPTICAL POTENTIAL
PARAMETERS RECOMMENDED BY LAGRANGE /20/.
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=55-59, 91
CALCULATED WITH CASTHY CODE /10/.
MT=102 RADIATIVE CAPTURE
CALCULATED WITH CASTHY CODE /10/.
DIRECT AND SEMI-DIRECT CAPTURE CROSS SECTIONS WERE ESTIMATED
WITH DSD CODE /21/ AND ADDED TO THE CASTHY CALCULATION.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
BELOW 300 KEV: CALCULATED WITH CASTHY CODE /10/
ABOVE 500 KEV: CALCULATED WITH ECIS CODE /19/
MT=16,17,18
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MT=51,52,53,54
SUM OF ECIS AND CASTHY CALCULATIONS.
MT=55-59, 91
CALCULATED WITH CASTHY CODE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
CALCULATED WITH EGNASH /22/.
MT=18
MAXWELLIAN FISSION SPECTRUM WITH TEMPERATURE ESTIMATED FROM
SYSTEMATICS OF HOWERTON AND DOYAS /23/. THE RATIOS OF
MULTI-CHANCE FISSION TO TOTAL WERE ESTIMATED FROM STAPRE
CALCULATION/14/.
REFERENCES
1) IGARASI S. AND NAKAGAWA T.: JAERI-M 7175 (1977).
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) MOORE M.S. AND KEYWORTH G.A.: PHYS. REV., C3, 1656 (1971).
6) BENJAMIN R.W. ET AL.: NUCL. SCI. ENG. 47, 203 (1972).
7) MAGUIRE JR.H.T. ET AL.: NUCL. SCI. ENG., 89, 293 (1985).
8) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, PART B",
ACADEMIC PRESS (1984).
9) KIKUCHI Y.: JAERI-DATA/CODE 99-025 (1999) [IN JAPANESE].
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
11) IGNATYUK A.V. ET AL.: SOV. J. NUCL. PHYS., 42, 360 (1985).
12) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
13) SHURSHIKOV E.N. ET AL.: NUCL. DATA SHEETS, 49, 785 (1986).
14) KONSHIN V.A.: JAERI-RESEARCH 95-010 (1995).
15) FOMUSHKIN E.F. ET AL.: SOV. J. NUCL. PHYS., 31, 19 (1980).
16) VOROTNIKOV P.E. ET AL.: SOV. AT. ENERGY, 57, 504 (1985).
17) FOMUSHKIN E.F. ET AL.: INT. CONF. NUCLEAR DATA FOR SVIENCE
AND TECHNOLOGY, JUELICH, GERMANY, 13-17 MAY 1991, P.439
(1992).
18) FURSOV B.I. ET AL.: INT. CONF. NUCLEAR DATA FOR SCIENCE AND
TECHNOLOGY, TRIESTE, ITALY, 19-24 MAY 1997, PART. 1, P.488
(1997).
19) RAYNAL J.: IAEA SMR-9/8 (1970).
20) LAGRANGE CH. AND JARY J.: NEANDC(E) 198 "L" (1978).
21) KAWANO T.: PRIVATE COMMUNICATION (1999).
22) YAMAMURO. N.: JAERI-M 90-006 (1990).
YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).
23) HOWERTON R.J. AND DOYAS R.J.: NUCL. SCI. ENG., 46, 414
(1971).