91-PA-233 KINKI U.+ EVAL-MAR87 T.OHSAWA, M.INOUE AND T.NAKAGAWA
DIST-MAR02 REV2-FEB02 20020222
----JENDL-3.3 MATERIAL 9137
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
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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
87-03 RE-EVALUATION WAS PERFORMED FOR JENDL-3 BY T. OHSAWA,
M. INOUE (KYUSHU UNIVERSITY) AND T.NAKAGAWA(JAERI)
COMPILATION WAS MADE BY T.NAKAGAWA.
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF NU-P (MT=456) AND NU-D (MT=455)
MT=455 NUMBER OF DELAYED NEUTRONS
TAKEN FROM TUTTLE'S SEMI-EMPIRICAL FORMULA /1/. ENERGY
DEPENDENCE WAS IGNORED.
MT=456 NUMBER OF PROMPT NEUTRONS
BASED ON THE SEMI-EMPIRICAL FORMULA BY BOIS AND FREHAUT /2/.
MF=2, MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCES FOR SLBW FORMULA: FROM 1.0E-5 TO 16.5 EV
PARAMETERS WERE TAKEN FROM THE RECOMMENDATION BY MUGHABGHAB
/3/ AND MODIFIED TO REPRODUCE THERMAL CROSS SECTIONS AND
RESONANCE INTEGRAL OF CAPTURE/3/.
UNRESOLVED RESONANCE PARAMETERS: FROM 16.5 EV TO 40 KEV
AVERAGE RESONANCE PARAMETERS RECOMMENDED BY MUGHABGHAB /3/
WERE ADOPTED.
S0 = 0.75E-4, S1 = 1.5E-4, D-OBS = 0.59 EV,
GAMMA WIDTH = 0.047 EV
(S1 WAS ADJUSTED WITH ASREP/5/ SO AS TO REPRODUCE TOTAL
AND CAPTURE CROSS SECTIONS AROUND 20 KEV.)
CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200-M/S RES. INTEG.
TOTAL 53.051 B
ELASTIC 13.021
FISSION 0.0 2.1 B
CAPTURE 40.031 864
MF=3 NEUTRON CROSS SECTIONS
BELOW 40 KEV, THE RESONANCE PARAMETERS WERE GIVEN. ABOVE 40
KEV, CROSS SECTIONS WERE EVALUATED AS FOLLOWS.
MT=1 TOTAL CROSS SECTION
CALCULATED WITH THE COUPLED-CHANNEL(CC) MODEL CODE
JUPITOR-1/5/. THE POTENTIAL PARAMETERS USED FOR THE CC-
CALCULATIONS ARE GIVEN BELOW.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF CAPTURE, INELASTIC,
FISSION, (N,2N) AND (N,3N) REACTION CROSS SECTIONS FROM THE
TOTAL CROSS SECTION.
MT=16 (N,2N)
CALCULATED WITH THE MODEL OF SEGEV ET AL./6/.
MT=17 (N,3N)
CALCULATED WITH THE MODEL OF SEGEV ET AL./6/.
MT=18 FISSION
CALCULATED USING THE EXPERIMENTAL DATA ON THE FISSION
PROBABILITY/7/.
MT=53,66 INELASTIC SCATTERING TO THE 3RD AND 16TH EXCITED
LEVELS(MEMBERS OF THE GROUND STATE ROTATIONAL BAND).
CALCULATED WITH THE CONSISTENT COMBINATION OF CC AND
HAUSER-FESHBACH(HF) METHODS (CC/HF METHOD)/8/. THE CODE
JUPITOR-1 WAS USED FOR THE CC CALCULATIONS, AND ELIESE-3
/9/ FOR THE HF CALCULATIONS.
MT=51-52,54-65,67-70,91 INELASTIC SCATTERING TO THE OTHER
DISCRETE AND CONTINUUM LEVELS.
COMPOUND NUCLEAR COMPONENT WAS CALCULATED WITH THE CODE
ELIESE-3 USING THE GENERALIZED TRANSMISSION COEFFICIENTS
CALCULATED WITH JUPITOR-1 FOR THE ENTRANCE CHANNEL. THE
LEVEL DENSITY PARAMETERS WERE TAKEN FROM GILBERT-CAMERON
/10/.
MT=102 CAPTURE
CALCULATED WITH THE CODE CASTHY/11/. THE AVERAGE RADIATIVE
WIDTH AND LEVEL SPACING USED TO NORMALIZE THE CALCULATION
ARE 40 MEV AND 0.79 EV, RESPECTIVELY/12/.
THE PARAMETERS FOR THE CC AND SPHERICAL OPTICAL POTENTIALS
WERE TAKEN FROM HAOUAT ET AL./13/ AND OHSAWA ET AL./14/
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 = 0.52 (FM)
ASO= 0.47 ASO= 0.47 (FM)
BETA2=0.190 ---
BETA4=0.071 ---
THE LEVEL SCHEME WAS TAKEN FROM NUCLEAR DATA SHEETS/15/,
EXCEPT THE 300.4 KEV-LEVEL, FOR WHICH 7/2- WAS ADOPTED
INSTEAD OF 7/2+ ACCORDING TO THE SUGGESTION OF GONZALEZ/16/.
NO. ENERGY(MEV) SPIN-PARITY
GS 0.0 3/2-
1 0.0067 1/2-
2 0.0572 7/2-
3 0.0706 5/2-
4 0.0865 5/2+
5 0.0947 3/2+
6 0.1036 7/2+
7 0.1090 9/2+
8 0.1634 11/2+
9 0.1691 1/2+
10 0.1792 9/2-
11 0.2017 3/2+
12 0.2123 5/2+
13 0.2379 9/2+
14 0.2573 5/2-
15 0.2796 7/2+
16 0.3004 7/2-
17 0.3061 7/2+
18 0.3661 9/2+
19 0.4477 3/2-
20 0.4546 3/2+
CONTINUUM LEVELS WERE ASSUMED ABOVE 0.5 MEV. THE LEVEL
DENSITY PARAMETERS WERE TAKEN FROM GILBERT-CAMERON/7/.
MT=251 MU-BAR
CALCULATED FROM ANGULAR DISTRIBUTIONS.
MF=4 ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS
MT=2 ELASTIC SCATTERING
CALCULATED WITH THE CC/HF METHOD.
MT=51-70 INELASTIC SCATTERING
CALCULATED WITH THE CC/HF METHOD FOR THE 3RD AND 13TH
EXCITED LEVELS. FOR THE OTHER LEVELS, CALCULATIONS WITH
ELIESE-3 USING THE GENERALIZED TRANSMISSION COEFFICIENTS
FOR THE ENTRANCE CHANNEL WERE ADOPTED.
MT=91 INELASTIC SCATTERING TO THE CONTINUUM
ISOTROPIC DISTRIBUTION WAS ASSUMED IN THE LABORATORY
SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91 (N,2N), (N,3N) AND CONTINUUM INELASTIC
EVAPORATION SPECTRA BASED ON THE LEVEL DENSITY PARAMETERS
MT=18 FISSION
MAXWELL SPECTRUM (TAKEN FROM ENDF/B-V).
REFERENCES
1) TUTTLE, R.J.: INDC(NDS)-107/G, P.29 (1979).
2) BOIS, R. AND FREHAUT, J.: CEA-R-4791 (1976).
3) MUGHABGHAB, S.F: "NEUTRON CROSS SECTIONS", VOL. 1, PART B,
ACADEMIC PRESS (1984).
4) KIKUCHI, Y.: PRIVATE COMMUNICATION.
5) TAMURA, T.: REV. MOD. PHYS. 37, 679 (1965).
6) SEGEV, M. ET AL.: ANN. NUCL. ENERGY 7, 577 (1980).
7) GAVRON, A.: PHYS. REV. C13, 2374 (1978).
8) OHSAWA, T. ET AL.: PROC. CONF. NUCL. DATA FOR BASIC AND
APPLIED SCI. 2, 1193 (1985).
9) IGARASI, S.: JAERI-1223 (1973).
10) GILBERT, M. AND CAMERON,A.G.W.: CAN. J. PHYS., 43, 1446(1966).
11) IGARASI, S.: J. NUCL. SCI. TECHNOL.,12, 67 (1975).
12) HUSSEIN, Z. ET AL.: NUCL. SCI. ENG., 78, 370 (1981).
13) HAOUAT, G. ET AL.: IBID. 81, 419 (1982).
14) OHSAWA, T. ET AL.:J. NUCL. SCI. TECHNOL. 18, 408 (1980).
15) ELLIS, Y.A.: NUCL. DATA SHEETS, 24, 289 (1978).
16) GONZALEZ, L. ET AL.: NUCL. PHYS. A324, 126 (1979).