91-Pa-232
91-PA-232 TIT EVAL-AUG88 N.TAKAGI
DIST-SEP89 REV2-JUN94
----JENDL-3.2 MATERIAL 9134
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 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 ADOPTED
FROM THE EVALUATION BY BRADY AND ENGLAND/5/.
MT=456 PROMPT NEUTRONS PER FISSION
BASED ON SYSTEMATICS BY MANERO AND KONSHIN/6/, AND BY
HOWERTON/7/.
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 1176.23 B -
ELASTIC 12.23 B -
FISSION 700.00 B 313 B
CAPTURE 464.00 B 309 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 1 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.
ABOVE 1 EV, OPTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/8/. THE POTENTIAL PARAMETERS/9/ 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 EV, ASSUMED TO BE THE SAME AS SHAPE ELASTIC
SCATTERING CROSS SECTION CALCULATED WITH THE OPTICAL
MODEL. ABOVE 1 EV, OPTICAL MODEL CALCULATION WAS
ADOPTED.
MT=4, 91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/8/. NO EXCITED LEVELS WERE RECOMMENDED IN
REF./10/.
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 2 -
LEVELS ABOVE 50 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./11/.
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 700 BARNS WAS TAKEN FROM
REF./12/, AND 1/V FORM WAS ASSUMED BELOW 1 EV. FOR
ENERGIES ABOVE 1 EV, THE SHAPE WAS ASSUMED TO BE THE SAME
AS U-233 FISSION CROSS SECTION AND NORMALIZED TO THE
SYSTEMATICS BY BEHRENS AND HOWERTON/13/.
MT=102 CAPTURE CROSS SECTION
MEASURED THERMAL CROSS SECTION OF 464 BARNS WAS TAKEN FROM
REF./12/, AND 1/V FORM WAS ASSUMED BELOW 1 EV. THE CROSS
SECTION SHAPE NEAR 1 EV WAS ADJUSTED SO AS TO REPRODUCE
THE RESONANCE INTEGRAL/12/. ABOVE 1 EV, CALCULATED WITH
CASTHY. THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM
GAMMA-GAMMA = 0.040 EV AND LEVEL SPACING = 0.417 EV.
MT=251 MU-L
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,91 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/14/.
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) MANERO F. AND KONSHIN V.A.: AT. ENERGY REV.,10, 637 (1972).
7) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
9) OHSAWA T., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).
10) SCHMORAX M.R.: NUCL. DATA SHEETS, 36, 367 (1982).
11) GILBERT A., CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
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) BEHRENS J.W., HOWERTON R.J: NUCL. SCI. ENG., 65, 464, (1978).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).