90-Th-232
90-TH-232 KINKI U. EVAL-MAR87 T.OHSAWA
DIST-SEP89 REV2-AUG93
----JENDL-3.2 MATERIAL 9040
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 RE-VALUATION WAS MADE BY T. OHSAWA (KINKI UNIVERSITY).
THE FOLLOWING PARTS OF PREVIOUS EVALUATION /1/ WERE REVISED
WITH NEW ONE.
RESONANCE PARAMETERS, ELASTIC AND INELASTIC SCATTERING,
NU-P, NU-D, ENERGY DISTRIBUTIONS OF NEUTRONS.
88-09 FISSION CROSS SECTION WAS MODIFIED A LITTLE.
89-02 FISSION PRODUCT YIELDS (MF=8) WERE REPLACED WITH JNDC FP
DECAY FILE VERSION-2.
89-04 FISSION SPECTRUM WAS MODIFIED.
COMPILATION WAS MADE BY T. NAKAGAWA(JAERI).
93-08 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(5,455) RELATIVE ABUNDANCE OF THE 1-ST GROUP
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF PROMPT AND DELAYED NEUTRONS.
MT=455 DELAYED NEUTRONS PER FISSION
NU-D BASED ON TUTTLE'S RECOMMENDATION /2/.
MT=456 PROMPT NEUTRONS PER FISSION
TAKEN FROM DAVEY'S RECOMMENDATION /3/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED AND UNRESOLVED RESONANCE PARAMETERS
RESOLVED RESONANCES FOR MLBW FORMULA : 1.0E-5 EV - 3.5 KEV
THE PARAMETERS OF JENDL-2 WHICH WERE MAINLY BASED ON
REF./4/ AND BNL 325(3RD) WERE MODIFIED AS FOLLOWS:
(1) FOR 22 RESONANCES IN THE LOWER ENERGY REGION WHICH MAKE
MAJOR CONTRIBUTION TO THE RESONANCE INTEGRAL, THE NEW
PARAMETERS OF KOBAYASHI /5/ WERE ADOPTED;
(2) THE AVERAGE RADIATIVE WIDTH OF 24.7 MEV WERE ATTRIBUTED
TO THOSE RESONANCES FOR WHICH THE RADIATIVE WIDTH WAS
NOT KNOWN.
UNRESOLVED RESONANCES : 3.5 KEV - 50 KEV
AVERAGE RESONANCE PARAMETERS WERE GIVEN. THE ENERGY
DEPENDENT S0 AND S1 WERE CALCULATED SO AS TO REPRODUCE THE
TOTAL AND CAPTURE CROSS SECTIONS IN THIS REGION. FIXED
PARAMETERS :
GG = 0.0212 EV, D-OBS = 18.64 EV, R = 10.01 FM.
TYPICAL STRENGTH FUNCTIONS AT 10 KEV :
S0 = 0.93E-4, S1 = 1.96E-4
CALCULATED 2200-M/SEC CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/SEC RES. INTEG.
TOTAL 21.11 B ---
ELASTIC 13.70 B ---
FISSION 0.0 B 0.636 B
CAPTURE 7.40 B 84.4 B
MF=3 NEUTRON CROSS SECTIONS
BELOW 3.5 KEV :
BACKGROUND CROSS SECTION IS GIVEN FOR THE CAPTURE.
ABOVE 50 KEV :
MT=1 TOTAL
BASED ON THE EXPERIMENTAL DATA OF WHALEN/6/, FOSTER/7/ AND
FASOLI/8/ IN THE SIZE RESONANCE REGION, AND KOBAYASHI/9/,
WHALEN/6/ AND UTTLEY/10,11/ BELOW 1.5 MEV, AND OPTICAL
MODEL CALCULATION ABOVE 14 MEV.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF CAPTURE, INELASTIC,
FISSION, (N,2N), (N,3N) CROSS SECTIONS FROM THE TOTAL CROSS
SECTION.
MT=4 TOTAL INELASTIC SCATTERING CROSS SECTION
SUM OF PARTIAL INELASTIC SCATTERING CROSS SECTIONS.
MT=16 (N,2N)
CALCULATED WITH THE MODEL OF SEGEV ET AL./12/.
MT=17 (N,3N)
CALCULATED WITH THE MODEL OF SEGEV ET AL./12/.
MT=18 FISSION
THE RATIO DATA TH-232/U-235 OF BEHRENS/13/ WERE MULTIPLIED
WITH THE EVALUATED DATA/14/ OF U-235(N,F).
MT=51-52 INELASTIC SCATTERING TO THE 1ST AND 2ND LEVELS.
CALCULATED WITH CONSISTENT COMBINATION OF COUPLED-CHANNEL
(CC) AND HAUSER-FESHBACH(HF) METHODS (CC/HF METHOD)/15/.
THE CODE JUPITOR-1/16/ WAS USED FOR CC-CALCULATIONS,
ELIESE-3/17/ FOR THE HF-CALCULATIONS.
MT=55,59,62,66 INELASTIC SCATTERING TO THE 5TH, 9TH, 12TH
AND 16TH LEVELS.
COMPOUND NUCLEAR COMPONENT WAS CALCULATED WITH THE CODE
ELIESE-3 USING THE GENERALIZED TRANSMISSION COEFFICIENTS
CALCULATED WITH JUPITOR-1 FOR THE ENTRANCE CHANNEL. DIRECT
REACTION COMPONENT WAS CALCULATED WITH THE CODE DWUCK/18/.
MT=53,54,56-58,60,61,63-65,67-70,91 INELASTIC SCATTERING
TO THE OTHER DISCRETE AND CONTINUUM LEVELS.
CALCULATED WITH ELIESE-3 USING THE GENERALIZED TRANS-
MISSION COEFFICIENTS FOR THE ENTRANCE CHANNEL.
MT=102 CAPTURE
BASED ON THE MEASUREMENT OF KOBAYASHI/19/ AND CALCULATION
WITH THE CODE CASTHY/20/.
THE PARAMETERS FOR THE CC AND SPHERICAL OPTICAL POTENTIALS
WERE TAKEN FROM HAOUAT ET AL./21/ AND OHSAWA ET AL./22/,
RESPECTIVELY:
CC SOM
V = 46.4-0.3*EN V = 41.0-0.05*EN (MEV)
WS = 3.6+0.4*EN WS = 6.4+0.15*SQRT(EN)(MEV)
VSO= 6.2 VSO= 7.0 (MEV)
R = 1.26 R = 1.31 (FM)
RS = 1.26 RS = 1.38 (FM)
RSO= 1.12 RSO= 1.31 (FM)
A = 0.63 A = 0.47 (FM)
AS = 0.52 AS = 0.47 (FM)
ASO= 0.47 ASO= 0.47 (FM)
BETA2=0.190
BETA4=0.071
THE LEVEL SCHEME WAS TAKEN FROM REF./23/.
NO. ENERGY(MEV) SPIN-PARITY
GS 0 0+
1 0.049 2+
2 0.162 4+
3 0.333 6+
4 0.557 8+
5 0.714 1-
6 0.730 0+
7 0.7741 2+
8 0.7743 3-
9 0.785 2+
10 0.830 3-
11 0.873 4+
12 0.883 5-
13 0.889 4+
14 0.960 5+
15 1.054 2-
16 1.073 2+
17 1.0777 1-
18 1.078 0+
19 1.094 3+
20 1.105 3-
CONTINUUM LEVELS WERE ASSUMED ABOVE 1.110MEV.
THE LEVEL DENSITY PARAMETERS OF GILBERT AND CAMERON/24/
WERE USED.
MT=251 MU-BAR
CALCULATED WITH THE OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 ELASTIC SCATTERING
CALCULATED WITH CC/HF METHOD/15/.
MT=51-70 INELASTIC
CALCULATED WITH CC/HF METHOD/15/ AND DWBA/18/.
MT=16,17,18,91 (N,2N), (N,3N), FISSION AND CONTINUUM INELASTIC
ASSUMED TO BE ISOTROPIC IN THE LAB SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91 (N,2N), (N,3N) AND CONTINUUM INELASTIC
CALCULATED WITH PEGASUS/25/.
MT=18 FISSION
MAXWELL SPECTRUM. THE TEMPERATURE PARAMETERS WERE ESTIMATED
FROM THE SYSTEMATICS OF HOWERTON-DOYAS/26/.
MT=455 DELAYED NEUTRONS
SPECTRUM EVAUATED BY SAPHIER ET AL./27/ WAS ADOPTED.
RELATIVE ABUNDANCE WAS TAKEN FROM REF./28/.
REFERENCES
1) OHSAWA,T., ET AL.; J. NUCL. SCI. TECHNOL., 18, 408 (1981).
2) TUTTLE,R.J., ET AL.; INDC(NDS)-107/G, P.29 (1979).
3) DAVEY,W.G.; NUCL. SCI. ENG., 44, 345 (1971).
4) RAHN,F., ET AL.; PHYS. REV., C6, 1854 (1972).
5) KOBAYASHI,K.; PRIVATE COMMUNICATION (1986).
6) WHALEN,F.F., AND SMITH,A.B.; NUCL. SCI. ENG., 67, 129 (1978).
7) FOSTER,D.G. ET AL.; PRIVATE COMMUNICATION (1967); PHYS. REV.
C3, 596 (1971)
8) FASOLI,U., ET AL.; NUCL. PHYS., A151, 369 (1970).
9) KOBAYASHI,K., ET AL.; NUCL. SCI. ENG., 65, 347 (1978).
10) UTTLEY,C.A., ET AL.; EANDC CONF. ON TOF METHODS, SACLAY (1961)
P.109
11) UTTLEY,C.A., ET AL.; PROC. 1ST CONF. ON NUCLEAR DATA FOR
REACTORS, PARIS (1966).
12) SEGEV,M., ET AL.; ANN. NUCL. ENERGY 5, 239 (1978).
13) BEHRENS,J.W., ET AL.; UCID-17442 (1977); PHYS. LETT. 69B, 278
(1977).
14) MATSUNOBU,H.; PRIVATE COMMUNICATION (1979).
15) OHSAWA,T., ET AL.; PROC. INT. CONF. ON NUCLEAR DATA FOR BASIC
AND APPLIED SCIENCE (1985) VOL.2, P.1193
16) TAMURA,T.; REV. MOD. PHYS., 37, 679 (1965).
17) IGARASI,S.; JAERI-1223 (1973).
18) KUNZ,P.D.; COO-535-606 AND -613 (1969).
19) KOBAYASHI,K., ET AL; PREPRINT 1978 FALL MTG. AT. ENERGY SOC.
JAPAN, D23 (1978).
20) IGARASI,S. AND FUKAHORI,T.; JAERI 1321 (1991).
21) HAOUAT,G., ET AL.; NUCL. SCI. ENG., 81, 491 (1982).
22) OHSAWA,T. ET AL.; J. NUCL. SCI. TECHNOL., 18, 408 (1980).
23) CHAN,D.W.S., ET AL.; PHYS. REV., C26, 841 (1982).
24) GILBERT,A. AND CAMERON,A.G.W.; CAN. J. PHYS., 24, 63 (1965).
25) IIJIMA,S., ET AL.; JAERI-M 87-025, P.337 (1987).
26) HOWERTON,R.J. AND DOYAS,R.J.; NUCL.SCI. ENG., 46, 414 (1971).
27) SAPHIER,D., ET AL.; NUCL. SCI. ENG., 62, 660 (1977).
28) KEEPIN,G.R., ET AL.; PHYS. REV., 107, 1044 (1957).