21-SC- 45 KHI EVAL-AUG88 T.WATANABE
DIST-SEP89 REV2-SEP93
----JENDL-3.2 MATERIAL 2125
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 JENDL-2 MODIFIED BY T.WATANABE
(KAWASAKI HEAVY INDUSTRIES, LTD.)
93-09 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) PARAMETERS OF 3.295-KEV RESONANCE
(3,2), (3,102)
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2
MT=151 RESONANCE PARAMETERS : 1.0E-5 EV - 100 KEV
RESOLVED RESONANCES FOR MLBW FORMULA:
PARAMETERS WERE EVALUATED BASED ON EXPERIMENTAL DATA
/1/,/2/,/3/ AND MODIFIED TO REPRODUCE EXPERIMENTAL
TOTAL CROSS SECTIONS. NEGATIVE ENERGY LEVELS WERE ADDED
TO REPRODUCE THE TOTAL AND CAPTURE CROSS SECTIONS/4/ AT
THERMAL AND THE TOTAL CROSS SECTION /5/ AT 2 KEV. FOR
JENDL-3.2, CAPTURE WIDTH OF 3.295-KEV RESONANCE WAS
CHANGED TO 0.71 EV/4/.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/SEC RES. INTEG.
ELASTIC 22.48 B -
CAPTURE 27.14 B 11.85 B
TOTAL 49.62 B -
MF=3 NEUTRON CROSS SECTIONS : ABOVE 100 KEV
MT=1,2,4,51-74,91,102 TOTAL, ELASTIC, INELASTIC AND CAPTURE
CALCULATED WITH OPTICAL AND STATISTICAL MODEL. DIRECT
INELASTIC REACTION CROSS SECTIONS WERE EVALUATED WITH
DWBA /6/ AND ADDED TO COMPOUND PROCESSES. STATISTICAL
MODEL CALCULATION WITH CASTHY CODE /7/ WAS PERFORMED.
MT=102 CAPTURE CROSS SECTION WAS NORMALIZED TO THE
EXPERIMENTAL DATA OF VOIGNIER+/8/, 11.2 MB AT 500 KEV.
DIRECT CAPTURE CROSS SECTION WAS CALCULATED FROM A
SIMPLE FORMULA OF BENZI AND REFFO/9/ AND NORMALIZED TO
1.0 MB AT 14.0 MEV.
THE SPHERICAL OPTICAL POTENTIAL PARAMETERS WERE EVALUATED
TO REPRODUCE TOTAL EXPERIMENTAL CROSS SECTIONS
/10,11,12/.
V = 56.2 - 0.3244*EN MEV R0= 1.155 FM A0= 0.666 FM
WS= 8.638-0.003093*EN MEV RS= 1.473 FM B = 0.262 FM
VSO=5.254 MEV RSO=1.003 FM ASO=0.485 FM
THE LEVEL SCHEME TAKEN FROM REF./13/:
NO. ENERGY(MEV) SPIN-PARITY BETA
G.S 0.0 7/2-
1 0.012396 3/2+
2 0.37659 3/2- 0.108
3 0.543 5/2+
4 0.72017 5/2- 0.0867
5 0.9392 1/2+ 0.0211
6 0.97461 7/2+
7 1.0672 3/2- 0.0586
8 1.23723 11/2- 0.143
9 1.30342 3/2+
10 1.40887 7/2-
11 1.43367 9/2+
12 1.5564 3/2-
13 1.66231 9/2- 0.0843
14 1.8004 5/2+
CONTINUUM LEVELS ASSUMED ABOVE 1.9 MEV
LEVEL DENSITY PARAMETERS WERE EVALUATED USING D0/4/,
AND LEVEL DATA /13/.
A T EX SIG**2(0)
21-SC-45 7.855 1.282 10.08 7.602
21-SC-46 7.231 1.268 7.328 7.867
MT=16 (N,2N)
THE JENDL-2 DATA WERE MODIFIED BY USING EXPERIMENTAL
DATA /14/.
MT=103 (N,P)
TAKEN FROM COMPILATION BY ALLEY AND LESSLER /15/
MT=107 (N,ALPHA)
SAME AS MT=103, BUT SLIGHTLY MODIFIED TO REPRODUCE
EXPERIMENTAL DATA/14/.
MT=251 MU-BAR
CALCULATED FROM THE DATA IN MF=4.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 CALCULATED WITH OPTICAL MODEL.
MT=51-91 CALCULATED WITH HAUSER-FESHBACH FORMULA ADDED WITH
DIRECT REACTION.
MT=16 ISOTROPIC IN THE LABORATORY SYSTEM
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
CALCULATED WITH SINCROS /16/.
REFERENCES
1) LIOU, H.I. ET AL.: NUCL. SCI. ENG. 67, 326 (1978).
2) KENNY, M.J. ET AL.: AUSTRALIAN J. PHYS. 30, 605 (1977).
3) ALLEN, B.J. ET AL.: NUCL. SCI. ENG. 82, 230 (1982).
4) MUGHABGHAB, S.F., ET AL: 'NEUTRON CROSS SECTIONS VOL.1 PART A'
ACADEMIC PRESS (1981)
5) FUJITA, Y: J. NUCL. SCI. TECHNOL. 20, 191 (1983).
6) KUNZ, P.D.: UNPUBLISHED (1974).
7) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).
8) VOIGNIER, J, ET AL.: NUCL. SCI. ENG. )3, 43 (1986). DATA WERE
TAKEN FROM EXFOR
9) BENZI, V. AND REFFO, G.: CCDN-NW/10 (1969).
10) POENITZ, W.P. AND WHALEN, J.F.: ANL/NDM-80 (1983).
11) BARNARD, E. ET AL.: Z. PHYS. 245, 36 (1971).
12) FOSTER, JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3, 576 (1971).
13) BURROWS, T.W.: NUCLEAR DATA SHEETS 40, 216 (1983).
14) IKEDA, Y., ET AL.: JAERI 1312 (1988).
15) ALLEY, W.E. AND LESSLER, R.M: NUCLEAR DATA TABLES A11,648
(1973).
16) YAMAMURO, N.: JAERI-M 88-140 (1988).