90-TH-234 KINKI U. EVAL-JUL87 T.OHSAWA
DIST-SEP89 REV2-JUN94
----JENDL-3.2 MATERIAL 9046
-----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
UNIV.). DETAILS OF THE EVALUATION ARE DESCRIBED IN REF.
/1/.
83-11 FISSION SPECTRUM WAS GIVEN. 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 CAPTURE CROSS SECTION AT 0.0253 EV
/7/ WAS EXTRAPOLATED ON AN 1/V BASIS UP TO AN ENERGY OF 15
EV. THE FISSION CROSS SECTION AT 0.0253 EV IS LESS THAN 0.02
BARN /8/, THEREFORE IT WAS ASSUMED TO 0.0 BARN.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS)
2200-M/S RES. INTEG.
TOTAL 14.75 -
ELASTIC 13.0 -
FISSION 0.0 0.26
CAPTURE 1.75 93.7
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=4,51-67,91 INELASTIC SCATTERING CROSS SECTION
STATISTICAL AND OPTICAL MODEL CALCULATIONS.
LEVEL SCHEME OF TH-234 (ESTIMATED FROM SYSTEMATICS)
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0 +
1 0.048 2 +
2 0.160 4 +
3 0.336 6 +
4 0.576 8 +
5 0.730 0 +
6 0.767 2 +
7 0.785 2 +
8 0.853 4 +
9 0.882 1 -
10 0.889 4 +
11 0.942 3 -
12 0.987 6 +
13 1.050 5 -
14 1.053 6 +
15 1.073 8 +
16 1.206 7 +
17 1.277 8 +
LEVELS ABOVE 1.06 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
FISSION PROBABILITY DEDUCED FROM DIRECT REACTION /12/ AND
SYSTEMATICS OF BEHRENS /13/ WERE USED TO OBTAIN 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 OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-67,91
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 WERE GIVEN.
MT=18
FISSION SPECTRUM WAS ESTIMATED FROM Z**2/A SYSTEMATICS
OF 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) HARVEY B.G. AND PARSONS B.I.: PHYS. REV., 80, 1098 (1950).
8) OSBORNE C. AND COVEYOU I.: MON-P-178, P.10 (1948), AS CITED IN
HUIZENGA J.R. ET AL. "THE ACTINIDE ELEMENTS", NATIONAL NUCLEAR
ENERGY SERIESEM DIV. IV, VOL.14A (ED. SEABORG ET AL.) P.839
(1954).
9) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981).
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
11) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978).
12) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974).
13) BEHRENS J.W.: UCID-17509-2 (1977); PHYS. REV. LETT. 39, 68
(1977).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).