91-PA-231 KINKI U.+ EVAL-MAR87 T.OHSAWA, M.INOUE AND T.NAKAGAWA
DIST-MAR02 REV2-FEB02 20020222
----JENDL-3.3 MATERIAL 9131
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
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 NEW EVALUATION WAS PERFORMED FOR JENDL-3 BY T. OHSAWA AND
M. INOUE.
87-07 RESONANCE PARAMETERS WERE EVALUATED BY T.NAKAGAWA(JAERI).
88-07 UNRESOLVED RESONANCE REGION WAS MODIFIED.
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 MT'S = 455 AND 456.
MT=455 DELAYED NEUTRONS
DECAY CONSTS WERE ASSUMED TO BE SAME AS THORIUM.
NU-D WAS EVALUATED ON THE BASIS OF TUTTLE'S RECOMMENDA-
TION/1/.
MT=456 NUMBER OF PROMPT NEUTRONS PER FISSION
BASED ON THE BOIS-FREHAUT'S SEMI-EMPIRICAL FORMULA /2/.
MF=2, MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCES FOR SLBW FORMULA: 1.0-5 - 115 EV
NEUTRON AND RADIATIVE WIDTHS WERE MAINLY ADOPTED FROM
HUSSEIN ET AL./3/, AND FISSION WIDTH ESTIMATED FROM THE
DATA OF FISSION AREA MEASURED BY PLATTERD ET AL. /4/.
FOR THE RESONANCES WHOSE FISSION AREA WAS NOT MEASURED,
AN AVERAGE VALUE OF 40 MICRO-EV WAS ASSUMED. A NEGATIVE
RESONANCE WAS GIVEN ON THE BASIS OF RECOMMENDATION BY
MUGHABGHAB /5/ TO REPRODUCE RECOMMENDED THERMAL CROSS
SECTIONS /5/.
UNRESOLVED RESONANCES : 115 EV - 40 KEV
PARAMETERS WERE BASED ON THE AVERAGE VALUES OBTAINED FROM
THE RESOLVED RESONANCE PARAMETERS. S1 WAS DETERMINED
FROM THE OPTICAL MODEL CALCULATION. SCATTERING RADIUS WAS
ADJUSTED SO AS TO REPRODUCE ELASTIC SCATTERING AT 40 KEV.
S0 = 0.90E-4, S1 = 1.2E-4, D-OBS = 0.47EV,
RADIATIVE WIDTH = 0.040 EV, R = 9.05 FM
BACKGROUND CROSS SECTION WAS GIVEN TO THE CAPTURE CROSS
SECTION TO CONNECT SMOOTHLY TO THAT IN HIGH ENERGY REGION.
CALCULATED 2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S RESONANCE INTEGRALS
TOTAL 210.69 B -
ELASTIC 9.954 -
FISSION 0.0196 4.61 B
CAPTURE 200.72 596 B
MF=3 NEUTRON CROSS SECTIONS
CROSS SECTION WERE REPRESENTED WITH RESONANCE PARAMETERS
BELOW 40 KEV. ABOVE THIS ENERGY, CROSS SECTIONS WERE
EVALUATED AS FOLLOWS.
MT=1 TOTAL CROSS SECTION
CALCULATED WITH THE COUPLED-CHANNEL(CC) MODEL CODE
JUPITOR-1/6/. 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./7/.
MT=17 (N,3N)
CALCULATED WITH THE MODEL OF SEGEV ET AL./7/.
MT=18 FISSION
BASED ON THE EXPERIMENTAL DATA OF PLATTARD/4/ BELOW 12 MEV.
ABOVE 12 MEV, THE EVALUATION OF MANN/9/ WAS ADOPTED AFTER
APPROPRIATE RENORMALIZATION.
MT=53,63 INELASTIC SCATTERING TO THE 3RD AND 13TH EXCITED
LEVELS(MEMBERS OF THE GROUND STATE ROTATIONAL BAND).
CALCULATED WITH THE CONSISTENT COMBINATION OF CC AND
HAUSER-FESHBACH(HF) METHODS (CC/HF METHOD)/9/. THE CODE
JUPITOR-1 WAS USED FOR THE CC CALCULATIONS, AND ELIESE-3
/10/ FOR THE HF CALCULATIONS.
MT=51-52,54-62,64-70,91 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
/11/.
MT=102 CAPTURE
CALCULATED WITH THE CODE CASTHY/12/. THE AVERAGE RADIATIVE
WIDTH AND LEVEL SPACING USED TO NORMALIZE THE CALCULATION
ARE 40 MEV AND 0.47 EV, RESPECTIVELY/3/.
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/.
NO. ENERGY(MEV) SPIN-PARITY
GS 0.0 3/2-
1 0.0093 1/2-
2 0.0585 7/2-
3 0.0778 5/2-
4 0.0842 5/2+
5 0.1013 7/2+
6 0.1029 3/2+
7 0.1116 9/2+
8 0.1340 11/2+
9 0.1693 11/2-
10 0.1741 5/2-
11 0.1835 5/2+
12 0.189 13/2+
13 0.2183 7/2-
14 0.2473 7/2+
15 0.2720 9/2-
16 0.287 1/2+
17 0.3179 3/2+
18 0.3202 3/2-
19 0.3400 11/2-
20 0.3518 5/2-
CONTINUUM LEVELS WERE ASSUMED ABOVE 0.38 MEV. THE LEVEL
DENSITY PARAMETERS WERE TAKEN FROM GILBERT-CAMERON/11/.
MT=251 MU-BAR
CALCULATED WITH THE OPTICAL MODEL.
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, AND ISOTROPIC
DISTRIBUTIONS WERE ASSUMED ABOVE 5.0 MEV BECAUSE OF ZERO
CROSS SECTIONS.
MT=91 INELASTIC SCATTERING TO THE CONTINUUM
ISOTROPIC DISTRIBUTIONS IN LAB. SYSTEM WAS ASSUMED.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91 (N,2N), (N,3N) AND CONTINUUM INELASTIC
EVAPORATION SPECTRA.
MT=18 FISSION
MAXWELL SPECTRUM (TAKEN FROM ENDF/B-V).
REFERENCES
1) TUTTLE, R.J.; INDC(NDS)-107/G (1979).
2) BOIS, R. AND FREHAUT, J.: CEA-R-4791 (1976).
3) HUSSEIN, A. ET AL.: NUCL. SCI. ENG., 78, 370 (1981).
4) PLATTARD, S. ET AL.: 79 KNOXVILLE, P.491
5) MUGHABGHAB, S.F.: "NEUTRON CROSS SECTIONS", VOL. 1, PART B,
ACADEMIC PRESS (1984).
6) TAMURA,T.: REV. MOD. PHYS. 37, 679 (1965).
7) SEGEV,M. ET AL.: ANN. NUCL. ENERGY 7, 577 (1980).
8) MANN, F.M.: HEDL-THE-78-100 (1979).
9) OHSAWA,T., ET AL.: 85 SANTA FE, 2 1193 (1985).
10) IGARASI, S.: JAERI-1223 (1973).
11) GILBERT, M. AND CAMERON, A.G.W.: CAN. J. PHYS., 43, 1446
(1966).
12) IGARASI, S.: J. NUCL. SCI. TECHNOL.,12, 67 (1975).
13) HAOUAT, G. ET AL.: IBID. 81, 419 (1982).
14) OHSAWA, T. ET AL.: J. NUCL. SCI. TECHNOL. 18, 408 (1980).
15) SCHMORAK, M.R.: NUCL. DATA SHEETS 21, 91 (1977).