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98-Cf-254 TIT EVAL-AUG87 N.TAKAGI
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9867
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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** Original data taken from: JEFF-3.1 **
** **
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***************************** JEFF-3.1 *************************
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** Original data taken from: JEFF-3.0 **
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***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JENDL-3.2 (DIST-SEP89 REV-JUN94)
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HISTORY
87-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF
TECHNOLOGY, TIT) /1/.
94-06 JENDL-3.2.
NU-P, NU-D AND NU-TOTAL WERE MODIFIED.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(1,452), (1,455), (1,456)
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF NU-P NAD NU-D.
MT=455 DELAYED NEUTRONS PER FISSION
AVERAGE VALUES OF SYSTEMATICS BY TUTTLE/2/, BENEDETTI ET
AL./3/ AND WALDO ET AL./4/ DECAY CONSTANTS WERE ASSUMED
TO BE THE SAME AS THOSE OF CF-252 EVALUATED BY BRADY AND
ENGLAND/5/.
MT=456 PROMPT NEUTRONS PER FISSION
CALCULATED FROM THE SEMI-EMPIRICAL FORMULA OF HOWERTON/6/.
A. Nouri (Data Bank)
use the same representation as for MT=452
(ENDF-6 recommendation): convert LNU=1
(polynomial (linear) representation) used in
JENDL-32 to tabular representation (LNU=2).
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 17.10 B -
ELASTIC 10.60 B -
FISSION 2.00 B 24.3 B
CAPTURE 4.50 B 6.5 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 120 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.
ABOVE 120 EV, OPTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/7/. THE POTENTIAL PARAMETERS/8/ USED ARE AS
FOLLOWS,
V = 43.4 - 0.107*EN (MEV)
WS= 6.95 - 0.339*EN + 0.0531*EN**2 (MEV)
WV= 0 , VSO = 7.0 (MEV)
R = RSO = 1.282 , RS = 1.29 (FM)
A = ASO = 0.60 , B = 0.5 (FM)
MT=2 ELASTIC SCATTERING CROSS SECTION
BELOW 120 EV, THE CONSTANT CROSS SECTION OF 10.6 BARNS WAS
ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS
SECTION CALCULATED WITH OPTICAL MODEL. ABOVE THIS ENERGY,
OPTICAL MODEL CALCULATION WAS ADOPTED.
MT=4,51,91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/7/. THE LEVEL SCHEME WAS TAKEN FROM REF./9/.
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 0 +
1 45.0 2 +
LEVELS ABOVE 140 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./10/.
MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS
CALCULATED WITH EVAPORATION MODEL.
MT=18 FISSION CROSS SECTION
THE THERMAL CROSS SECTION OF 2.0 BARNS WAS ESTIMATED FROM
THE RATIO OF FISSION AND CAPTURE CROSS SECTIONS AT 1 EV
AND MEASURED CAPTURE CROSS SECTION AT 0.0253 EV. THE FORM
OF 1/V WAS ASSUMED BELOW 120 EV. FOR ENERGY ABOVE 120 EV,
THE SHAPE OF CF-252 FISSION CROSS SECTION WAS ADOPTED AND
IT WAS NORMALIZED TO THE SYSTEMATICS OF BEHRENS AND
HOWERTON/11/.
MT=102 CAPTURE CROSS SECTION
MEASURED THERMAL CROSS SECTION OF 4.5 BARNS WAS TAKEN FROM
REF./12/, AND 1/V FORM WAS ASSUMED BELOW 120 EV. ABOVE
120 EV, THE CROSS SECTION WAS CALCULATED WITH CASTHY. THE
GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM GAMMA-GAMMA
= 0.040 EV AND LEVEL SPACING = 240 EV.
MT=251 MU-L
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51,91 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) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979),
3) BENEDETTI G. ET AL.: NUCL. SCI. ENG., 80, 379 (1982).
4) WALDO R. ET AL.: PHYS. REV., C23, 1113 (1981).
5) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129 (1989).
6) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
7) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
8) IGARASI S. AND NAKAGAWA T.: JAERI-M 8342 (1979).
9) SCHMORAK M.R.: NUCL. DATA SHEETS, 32, 87 (1981).
10) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
11) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464(1978).
12) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON
RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,
Z=61-100", ACADEMIC PRESS (1984).
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).
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