88-RA-223 TIT EVAL-AUG88 N.TAKAGI
DIST-MAR02 REV2-FEB02 20020222
----JENDL-3.3 MATERIAL 8825
-----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)
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
EVALUATED WITH SEMI EMPIRICAL FORMULA OF HOWERTON/1/.
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS
NO RESONANCE PARAMETERS WERE GIVEN.
2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 143.10 B -
ELASTIC 12.40 B -
FISSION 0.70 B 1.06 B
CAPTURE 130.00 B 435 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 4 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.
ABOVE 4 EV, OPTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/2/. THE POTENTIAL PARAMETERS/3/ 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 4 EV, THE CONSTANT CROSS SECTION OF 12.4 BARNS WAS
ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS
SECTION CALCULATED WITH OPTICAL MODEL. ABOVE THIS ENERGY,
OPTICAL MODEL CALCULATION WAS ADOPTED.
MT=4,51-52,91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/2/. THE LEVEL SCHEME WAS TAKEN FROM REF. 4.
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 1/2 +
1 50.19 3/2 -
2 61.53 5/2 +
3 79.77 3/2 -
4 123.91 5/2 -
5 130.27 7/2 +
6 174.72 9/2 +
7 174.78 7/2 -
8 247.47 9/2 -
9 280.31 3/2 +
10 286.16 3/2 +
11 329.95 3/2 -
12 334.52 3/2 +
13 342.50 3/2 +
14 342.92 5/2 +
LEVELS ABOVE 369.43 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF. 5.
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 0.7 BARN WAS TAKEN FROM
REF. 6 , AND 1/V FORM WAS ASSUMED BELOW 4 EV. ABOVE THIS
ENERGY, THE CONSTANT CROSS SECTION WAS ADOPTED.
MT=102 CAPTURE CROSS SECTION
MEASURED THERMAL CROSS SECTION OF 130 BARNS WAS TAKEN FROM
REF. 6 , AND 1/V FORM WAS ASSUMED BELOW 4 EV. ABOVE 4 EV,
CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH FUNCTION
WAS ESTIMATED FROM GAMMA-GAMMA = 0.040 EV AND LEVEL
SPACING = 8 EV.
MT=251 MU-L
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-64,91 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/7/.
REFERENCES
1) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
2) IGARASI S.: J.NUCL.SCI.TECHNOL.,12,67 (1975).
3) OHSAWA T., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).
4) MAPLES C.: NUCL. DATA SHEETS, 22, 243 (1977).
5) GILBERT A., CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
6) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON
RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,
Z=61-100", ACADEMIC PRESS (1984).
7) SMITH A.B. ET AL.: ANL/NDM-50 (1979).