90-TH-230 KINKI U. EVAL-JUL87 T.OHSAWA
DIST-SEP89 REV2-JUN94
----JENDL-3.2 MATERIAL 9034
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
81-04 EVALUATION FOR JENDL-2 WAS MADE BY T. OHSAWA AND M. OHTA
(KYUSHU UNIVERSITY: PRESENT ADDRESS OF OHSAWA IS KINKI
UNIVERSITY). DETAILS OF EVALUATION ARE DESCRIBED IN REF.
/1/.
83-11 FISSION SPECTRUM WAS ADDED. RESONANCE PARAMETERS, AND
TOTAL, (N,2N) AND (N,3N) CROSS SECTIONS WERE MODIFIED.
87-07 EVALUATION FOR JENDL-2 WAS ADOPTED TO JENDL-3. BUT RE-
CALCULATION OF CROSS SECTIONS AND ANGULAR DISTRIBUTIONS
WAS MADE WITH THE SAME OMP AND LEVEL DENSITY PARAMETERS.
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-229 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
RESONANCE REGION IS BELOW 564.26 EV. THE MLBW FORMULA WAS
SELECTED TO REPRODUCE RESONANCE CROSS SECTIONS. A TOTAL
NUMBER OF 28 RESONANCES UP TO 563 EV MEASURED BY KALEBIN ET
AL. /7/ WERE ADOPTED IN THE PRESENT EVALUATION.
A BACKGROUND TERM WITH 1/V DEPENDENCE WAS ADDED IN ORDER TO
REPRODUCE THE THERMAL CAPTURE CROSS SECTION.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS)
2200-M/S RES. INTEG.
TOTAL 32.32 -
ELASTIC 9.774 -
FISSION 0.0 1.08
CAPTURE 22.55 1040
MF=3 NEUTRON CROSS SECTIONS
BELOW 564.26 EV IS THE RESONANCE REGION WHERE THE
BACKGROUND CROSS SECTIONS ARE GIVEN. ABOVE 564.26 EV, THE
CROSS SECTIONS WERE EVALUATED AS FOLLOWS.
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 /8/.
MT=2 ELASTIC SCATTERING CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS USING THE CODE
CASTHY /9/.
MT=4,51-63,91 INELASTIC SCATTERING CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS.
LEVEL SCHEME OF TH-230 /10/.
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1 0.0534 2 +
2 0.173 4 +
3 0.357 6 +
4 0.506 1 -
5 0.571 3 -
6 0.635 0 +
7 0.678 2 +
8 0.682 5 -
9 0.781 2 +
10 0.881 4 +
11 0.951 1 -
12 1.009 2 +
13 1.012 3 -
LEVELS ABOVE 1.02 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 /11/.
MT=18 FISSION CROSS SECTION
EVALUATION WAS MADE ON THE BASIS OF THE DATA OF MUIR ET
AL. /12/ UP TO 2 MEV. ABOVE 2 MEV, THE FISSION PROBABILITY
DATA OF BACK ET AL. /13/ WERE USED TO CALCULATE THE FISSION
CROSS SECTION.
MT=102 CAPTURE CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS WITH GAMMA-RAY
STRENGTH FUNCTION OF 0.00791.
MT=251 MU-BAR
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-63,91
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 BY SMITH
ET AL. /14/.
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) KALEBIN S.M. ET AL.: SOV. J. ATOM. ENERGY 26, 588 (1969).
8) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981).
9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
10) LEDERER C.M. AND SHIRLY V.S. (ED.): TABLE OF ISOTOPES,
7TH EDITION (1978).
11) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978).
12) MUIR D.W. ET AL.: PROC. 3RD CONF. ON NEUTRON CROSS SECTIONS
AND TECHNOLOGY, KNOXVILLE (1971), P.292.
13) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).