88-RA-226 TIT EVAL-AUG88 N.TAKAGI
DIST-MAR02 REV3-FEB02 20020222
----JENDL-3.3 MATERIAL 8834
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
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JENDL-3.2 data were automatically transformed to JENDL-3.3.
Interpolation of spectra: 22 (unit base interpolation)
(3,251) deleted, T-matrix of (4,2) deleted, and others.
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HISTORY
88-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF
TECHNOLOGY, TIT)/1/
93-11 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,1), (3,18) BELOW 6 MEV.
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
EVALUATED WITH SEMI EMPIRICAL FORMULA OF HOWERTON/2/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV TO 1000 EV.
MULTI-LEVEL BREIT-WIGNER FORMULA WAS ADOPTED.
PARAMETERS WERE TAKEN FROM THOSE BY IVANOV/3/.
NO FISSION WIDTH WAS GIVEN FOR ALL THE RESONANCES.
AVERAGE GAM-G = 0.0258 EV
EFFECTIVE SCATTERING RADIUS = 9.60 FM
2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 22.58 B -
ELASTIC 9.80 B -
FISSION 7.0E-6 B 0.0119 B
CAPTURE 12.78 B 285.6 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE
PARAMETERS. ABOVE 1 KEV, OPTICAL MODEL CALCULATION WAS
MADE WITH CASTHY/4/. THE POTENTIAL PARAMETERS/5/ USED
ARE AS FOLLOWS,
V = 41.0 - 0.05*EN (MEV)
WS= 6.4 - 0.15*SQRT(EN) (MEV)
WV= 0 , VSO = 7.0 (MEV)
R = RSO = 1.31 , RS = 1.38 (FM)
A = ASO = 0.47 , B = 0.47 (FM)
MT=2 ELASTIC SCATTERING CROSS SECTION
BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE
PARAMETERS. ABOVE 1 KEV, OPTICAL MODEL CALCULATION WAS
ADOPTED.
MT=4,51-66,91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/4/. THE LEVEL SCHEME WAS TAKEN FROM REF./6/
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 0 +
1 67.67 2 +
2 211.54 4 +
3 253.73 1 -
4 321.54 3 -
5 416.60 6 +
6 446.20 5 -
7 626.90 7 -
8 650.00 0 +
9 669.40 8 +
10 824.60 0 +
11 857.90 9 -
12 873.70 2 +
13 960.00 10 +
14 1048.60 1 -
15 1070.50 2 -
16 1134.00 11 -
LEVELS ABOVE 1446 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./7/
MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS
CALCULATED WITH EVAPORATION MODEL.
MT=18 FISSION CROSS SECTION
MEASURED THERMAL CROSS SECTION OF 7 MICRO-BARN WAS TAKEN
FROM REF./8/, AND 1/V FORM WAS ASSUMED BELOW 10 EV. FOR
ENERGY REGION ABOVE 1 MEV, THE EVALUATION WAS BASED ON
EXPERIMENTAL DATA /9,10,11,12/, AND BETWEEN 15 EV AND
FISSION THRESHOLD, CROSS SECTION WAS ASSUMED TO BE THE
SAME AS THE VALUE AT 15 EV.
MT=102 CAPTURE CROSS SECTION
BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE
PARAMETERS. ABOVE 1 KEV, IT WAS CALCULATED WITH CASTHY.
THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM
GAMMA-GAMMA = 0.040 EV AND LEVEL SPACING = 30.3 EV.
MT=251 MU-L
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-66,91 CALCULATED WITH OPTICAL MODEL.
MT=16,17,18,37 ISOTROPIC IN THE LAB SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,37,91 EVAPORATION SPECTRA
OBTAINED FROM LEVEL DENSITY PARAMETERS.
MT=18 MAXWELLIAN FISSION SPECTRUM.
TEMPERATURE WAS ESTIMATED FROM Z**2/A DEPENDENCE/13/.
REFERENCES
1) TAKAGI N. ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990).
2) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
3) IVANOV R.N. ET AL.: AT. ENERG., 42, 505 (1977).
4) IGARASI S. AND FUKAFORI T.: JAERI 1321 (1991).
5) OHSAWA T., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).
6) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 50, 229 (1987).
7) GILBERT A., CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
8) NAKAHARA H. ET AL.: J. INORG. NUCL. CHEM., 38, 203 (1976).
9) NOBLES R.A ET AL.: NUCL. PHYS., 5, 211 (1958).
10) BABENKO JU.A. ET AL.: YAD. FIZ., 7, 269 (1968).
11) ZHAGROV E.A. ET AL.: NUCL. PHYS., A213, 436 (1973).
12) NEMILOV YU.A. ET AL.: YAD. FIZ., 37, 819 (1983).
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).