92-U -234 KAWASAKI EVAL-MAR87 T.WATANABE
DIST-SEP89 REV2-JUL93
----JENDL-3.2 MATERIAL 9225
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION FOR JENDL-3 WAS MADE BY T.WATANABE (KWASAKI
HEAVY IND.)
87-06 COMPILATION WAS MADE BY T.NAKAGAWA (JAERI)
93-07 JENDL-3.2.
MODIFIED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(1,452), (1,455), (1456) NEW EVALUATION
(3,2), (3,4), (3,51-91) NEW LEVEL SCHEME ADOPTED.
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF MT=455 AND 456.
MT=455 DELAYED NEUTRONS PER FISSION
SYSTEMATICS OF TUTTLE/1/. SIX GROUP DECAY CONSTANTS WERE
ADOPTED FROM BRADY ET AL./2/
MT=456 PROMPT NEUTRONS PER FISSION
BASED ON THE EXPERIMENTAL DATA BY MATHER ET AL./3/ NU-P OF
CF-252 SPONTANEOUS FISSION WAS ASSUMED TO BE 3.756.
MF=2 RESONANCE PARAMETERS
MT=251 RESONANCE PARAMETERS ; 1.0E-5 EV - 50 KEV
RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 EV - 1.5 KEV
PARAMETERS OF REF./4/ WERE ADOPTED AFTER MODIFICATION OF
AN AVERAGE RADIATIVE WIDTH TO 0.026 EV/5/. A NEGATIVE
LEVEL WAS ADDED AT -2.06 EV SO AS TO REPRODUCE THE CROSS
SECTIONS AT 0.0253 EV/5/.
TOTAL = 119.1 +- 1.3 B
ELASTIC = 19.6 +- 1.0 B
CAPTURE = 99.8 +- 1.3 B
UNRESOLVED RESONANCES : 1.5 KEV - 50 KEV
THE FOLLOWING PARAMETERS WERE GIVEN.
= 0.026 EV/2/, = 0.0 EV, D-OBS = 10.6 EV/2/,
S-0 = 0.96E-4 (CALCULATED WITH ECIS/6/),
S-1 = 1.197E-4 (ADJUSTED TO THE TOTAL CROSS SECTION
CALCULATED WITH ECIS/6/),
R = 9.70 FM (ADJUSTED TO THE TOTAL CROSS SECTION AT
50 KEV).
CALCULATED 2200M/S CROSS SECTIONS AND RESONANCE INTEGRALS.
2200 M/S RESONANCE INTEGRAL
TOTAL 119.2 B ---
ELASTIC 19.41 B ---
FISSION 6.22 MB 6.72 B
CAPTURE 99.75 B 632 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 50 KEV, RESONANCE PARAMETERS WERE EVALUATED.
BACKGROUND CROSS SECTIONS FOR THE FISSION WERE GIVEN IN THE
UNRESOLVED RESONANCE REGION.
MT=1,2,4,51-69,91,102 TOTAL, ELASTIC AND INELASTIC SCATTERING,
AND CAPTURE
CALCULATED WITH COUPLED-CHANNEL CODE ECIS/6/ AND SPHERICAL
OPTICAL AND STATISTICAL MODEL CODE CASTHY/7/.
THE DEFORMED OPTICAL POTENTIAL PARAMETERS OF LAGRANGE/8/
WERE ADOPTED FOR THE ECIS CALCULATION.
V = 46.42 - 0.3 * EN, RO = 1.26, AO = 0.63
WS = 3.72 + 0.4 * EN, RS = 1.26, B = 0.52
EN UP TO 10 MEV
= 7.72
EN ABOVE 10 MEV
VSO = 6.2 RSO= 1.12 ASO= 0.47
BETA2 = 0.194
BETA4 = 0.071
THE FOLLOWING SPHERICAL OPTICAL POTENTIAL PARAMETERS FOR THE
CASTHY CALCULATION WERE DETERMINED SO AS TO REPRODUCE THE
TOTAL CROSS SECTION CALCULATED WITH ECIS BY USING THE ABOVE
OMP.
V = 41.49 - 0.1359 * EN
WS = 9.284 - 0.2086 * EN+ 0.03225 * EN**2
(DERIVATIVE WOODS-SAXON FORM)
VSO= 4.248,
R = 1.315, RS = 1.381, RSO= 1.15
AO = 0.528, B = 0.372, ASO= 0.597
THE LEVEL SCHEME WAS TAKEN FROM REF./9/.
NO. ENERGY(MEV) SPIN-PARITY COUPLED LVL
G.S 0.0 0 + *
1 0.04348 2 + *
2 0.14334 4 + *
3 0.29606 6 + *
4 0.49702 8 + *
5 0.7412 10 + *
6 0.78628 1 -
7 0.80989 0 +
8 0.84930 3 -
9 0.85172 2 +
10 0.92672 2 +
11 0.94785 4 +
12 0.9626 5 -
13 0.9691 3 +
14 0.9895 2 -
15 1.0236 4 +
16 1.0238 3 -
17 1.0445 0 +
18 1.0854 2 +
19 1.0916 0 +
CONTINUUM LEVELS WERE ASSUMED ABOVE 1.126 MEV
LEVEL DENSITY PARAMETERS WERE EVALUATED USING D-OBS AND
EXCITED LEVEL DATA/2,6/.
A(1/MEV) T(MEV) EX(MEV) SIG**2(0)
92-U-234 29.349 0.4058 4.769 16.872
92-U-235 31.415 0.3914 4.231 14.378
THE GAMMA-RAY STRENGTH FUNCTION (=84.6E-4) WAS DETERMINED
BY NORMALIZING THE CAPTURE CROSS SECTION TO 0.46535 B AT 50
KEV WHICH WAS CALCULATED FROM ABOVE-MENTIONED UNRESOLVED
RESONANCE PARAMETERS.
MT=16,17 (N,2N) AND (N,3N)
JENDL-2 DATA CALCULATED WITH THE EVAPORATION MODEL WERE
RENORMALIZED SO THAT THEY MIGHT BE CONSISTENT WITH THE
FISSION AND COMPOUND FORMATION CROSS SECTIONS CALCULATED
WITH ECIS AND CASTHY.
MT=18 FISSION
EXPERIMENTAL DATA /10,11,12/ OF FISSION CROSS SECTION RATIO
TO U-235 WERE EVALUATED. FISSION CROSS SECTION WAS
OBTAINED BY MULTIPLYING THE U-235 FISSION CROSS SECTION/13/
TO THE RATIO.
MT=251 MU-L BAR
CALCULATED WITH ECIS AND CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-69,91 CALCULATED WITH ECIS AND CASTHY
MT=16,17,18 ASSUMED TO BE ISOTROPIC IN THE LAB. SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91 TABLE TYPE DATA WERE GIVEN
SPECTRA WERE CALCULATED WITH PREEQUILIBRIUM AND MULTI-
STEP EVAPORATION MODEL CODE PEGASUS /14/
MT=18
CALCULATED WITH THE FORMULA OF MADLAND AND NIX /15/.
CONSTANT COMPOUND NUCLEUS FORMATION CROSS SECTION MODEL
WAS ADOPTED.
TOTAL AVERAGE FF KINETIC ENERGY = 171.09 MEV
AVERAGE ENERGY RELEASE = 187.976 MEV
AVERAGE MASS NUMBER OF LIGHT FF = 95
AVERAGE MASS NUMBER OF HEAVY FF = 140
LEVEL DENSITY PARAMETER = A/10.0
REFERENCES
1) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979).
2) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129(1989).
3) MATHER D.S. ET AL.: NUCL. PHYS., 66, 149 (1965).
4) JAMES G.D. ET AL: PHY. REV., C15, 2083 (1977).
5) MUGHABGHAB S.F.:"NEUTRON CROSS SECTIONS, VOL 1, PART B",
ACADEMIC PRESS (1984).
6) RAYNAL J.: IAEA SMR-9/8 (1970).
7) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
8) LAGRANGE C.H.: NEANDC(E)-228 (1982).
9) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 40, 567 (1983). AND
ENSDF AS IS 1993.
10) BEHRENS J.W. AND CARLSON G.W.: NUCL. SCI. ENG., 63, 2501977).
11) MEADOWS J.W.: NUCL. SCI. ENG., 65, 171 (1978).
12) KANDA K. ET AL.: 1985 SANTA FE, 1, 569 (1986).
13) MATSUNOBU H.: JENDL-3 U-235 EVALUATION (1987).
14) IIJIMA S. ET AL.: TO BE PUBLISHED.
15) MADLAND D.G. AND NIX J.R.: NUCL. SCI. ENG., 81, 213 (1982).