90-TH-233 KINKI U. EVAL-JUL87 T.OHSAWA
DIST-MAR02 REV3-FEB02 20020222
----JENDL-3.3 MATERIAL 9043
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
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.
===========================================================
HISTORY
81-04 EVALUATION FOR JENDL-2 WAS MADE BY T. OHSAWA AND M. OHTA
(KYUSHU UNIVERSITY: PRESENT ADDRESS OF OHSAWA IS KINKI
UNIV.). DETAILS OF THE EVALUATION ARE DESCRIBED IN REF.
/1/.
83-11 FISSION SPECTRUM WAS ADDED. THE TOTAL, (N,2N) AND (N,3N)
CROSS SECTIONS WERE MODIFIED.
87-07 JENDL-2 DATA WERE ADOPTED FOR JENDL-3.
COMPILATION WAS MADE BY T.NAKAGAWA (JAERI).
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 TH-232 EVALUATED BY BRADY AND
ENGLAND/5/.
MT=456 PROMPT NEUTRONS PER FISSION
BASED ON THE SEMI-EMPIRICAL FORMULA OF HOWERTON /6/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCES
NO RESOLVED RESONANCES WERE ADOPTED, SINCE THERE WERE NO
MEASUREMENTS MADE. THE THERMAL CAPTURE CROSS SECTION OF
1450+-100 BARNS WAS ADOPTED FROM REF./7/, AND THE THERMAL
FISSION CROSS SECTION OF 15 BARNS FROM LLL EVALUATED NUCLEAR
DATA LIBRARY/8/. THE CAPTURE AND FISSION CROSS SECTIONS AT
0.0253 EV WERE EXTRAPOLATED UP TO 200 EV BY ASSUMING THE
FORM OF 1/V FOR THE FORMER, AND UP TO 20 KEV BY ASSUMING THE
FORM OF 1/V PLUS THE CONSTANT VALUE OF 0.3 BARNS FOR THE
LATTER.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS)
2200-M/S RES. INTEG.
TOTAL 1478.0 -
ELASTIC 13.0 -
FISSION 15.0 11.1
CAPTURE 1450.0 643
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
OPTICAL MODEL CALCULATION WITH THE FOLLOWING PARAMETERS:
V = 41.0 - 0.05*E (MEV),
WS = 6.4 + 0.15*SQRT(E) (MEV), -- DER. WOODS-SAXON --
VSO= 7.0 (MEV),
R0 = RSO = 1.31 (FM),
RS = 1.38 (FM),
A = B = ASO= 0.47 (FM).
THESE PARAMETERS WERE TAKEN FROM THOSE FOR TH-232 /9/.
MT=2 ELASTIC SCATTERING CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS USING THE CODE
CASTHY /10/.
MT=4,51-65,91 INELASTIC SCATTERING CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS.
LEVEL SCHEME OF TH-233 /11/.
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 1/2 +
1 0.01687 3/2 +
2 0.05456 5/2 +
3 0.09363 7/2 +
4 0.37121 5/2 +
5 0.53958 1/2 -
6 0.58393 1/2 +
7 0.6115 3/2 +
8 0.62902 5/2 +
9 0.6822 3/2 -
10 0.7135 1/2 +
11 0.7218 3/2 +
12 0.7695 5/2 +
13 0.8145 3/2 +
14 0.8914 3/2 +
15 0.9476 3/2 -
LEVELS ABOVE 0.95 MEV WERE ASSUMED TO BE OVERLAPPING.
MT=16,17 (N,2N) AND (N,3N) CROSS SECTIONS
CALCULATED BY MEANS OF THE EVAPORATION MODEL OF SEGEV AND
CANER /12/.
MT=18 FISSION CROSS SECTION
FISSION PROBABILITY DEDUCED FROM DIRECT REACTION /13, 14/
WAS USED TO CALCULATE THE FISSION CROSS SECTION.
MT=102 CAPTURE CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS WITH GAMMA-RAY
STRENGTH FUNCTION OF 0.00352.
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-65,91
STATISTICAL AND OPTICAL MODEL CALCULATIONS.
MT=16,17,18
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91
EVAPORATION SPECTRA.
MT=18
FISSION SPECTRUM ESTIMATED FROM Z**2/A SYSTEMATICS OF SMITH
ET AL. /15/
REFERENCES
1) OHSAWA T. AND OHTA M.: MEMOIRS FACULTY OF ENGINEERING,
KYUSHU UNIV. 40, 149 (1980).
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) JOHNSTONE F.J. AND HALPERIN J.: J. NUCL. ENERGY, 11, 95(1960).
8) UCRL-50400, VOL. 15, PART D (1977).
9) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981).
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
11) LEDERER C.M. AND SHIRLY V.S. (ED.): TABLE OF ISOTOPES,
7TH EDITION (1978).
12) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978).
13) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974).
14) CRAMER J.D. AND BRITT H.C.: NUCL. SCI. ENG. 41, 177 (1970).
15) SMITH A.B. ET AL.: ANL/NDM-50 (1979).