24-CR- 0 NEDAC EVAL-MAR87 T.ASAMI(NEDAC)
DIST-SEP89 REV2-DEC93
----JENDL-3.2 MATERIAL 2400
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE BY T.ASAMI.
88-12 MF/MT=3/107 MODIFIED.
89-08 MF/MT=15/102 MODIFIED.
93-12 JENDL-3.2.
GAMMA-RAY PRODUCTION DATA REVISED BY T.ASAMI (DATA ENG.)
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,1), (3,2) BETWEEN 300 KEV AND 4 MEV
(4,16-28), (4,91) TAKEN FROM JENDL FUSION FILE
(5,16-91) TAKEN FROM JENDL FUSION FILE
(12,102)
(13,3), (13,4)
(15,102)
***********************************************************
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JENDL FUSION FILE /1/ (AS IS AUG. 1993)
EVALUATED B.YU (CIAE) AND S.CHIBA (NDC/JAERI)
COMPILED BY B.YU.
ALL OF CROSS SECTINOS WERE TAKEN FROM JENDL-3. MF=6 OF
MT=16, 22, 28 AND 91 WERE CREATED FROM SINCROS-II /2/ AND
F15TOB/1/ PROGRAM. MODIFIED-KUMABE'S SYSTEMATICS /1/ WAS
USED. THE PRECOMPOUND/COMPOUND RATIO WAS CALCULATED BY
THE SINCROS-II CODE SYSTEM.
OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED
IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.
LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/3/.
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MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS
RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY
REGION FROM 1.0E-5 EV TO 300 KEV. THE DATA WERE CONSTRUCTED
FROM THE EVALUATED RESONANCE PARAMETERS FOR EACH CR ISOTOPE,
CONSIDERING THEIR ABUNDANCES IN THE CR ELEMENT/4/.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 3.38
CAPTURE 3.07 1.53
TOTAL 6.45
MF=3 NEUTRON CROSS SECTIONS
BELOW 300 KEV, BACKGROUND CROSS SECTION WAS GIVEN. AS THE
EVALUATED DATA ON THE RESONANCE PARAMETERS OF CR-53 WERE GIVEN
BELOW 120 KEV, THE CROSS SECTIONS OF CR-53 FOR TOTAL, ELASTIC
SCATTERING AND CAPTURE IN THIS ENERGY RANGE, MULTIPLIED BY ITS
ABUNDANCE, ARE PROVIDED AS THE BACKGROUND CROSS SECTIONS FOR
MT=1, 2 AND 102. ALL THE CROSS-SECTION DATA WERE DEDUCED FROM
THE EVALUATED ONES FOR FOUR STABLE ISOTOPES OF CR CONSIDERING
THEIR ABUNDANCES IN THE CR ELEMENT/4/, EXCEPT FOR THE TOTAL
CROSS SECTIONS IN THE ENERGIES ABOVE 300 KEV.
MT=1 TOTAL
THE DATA IN THE ENERGY RANGE ABOVE 300 KEV WERE EVALUATED BASED
ON THE EXPERIMENTAL DATA OF/5,6,7/. THE DATA IN REF./5/ WERE
USED TO DETERMINE THE FINE STRUCTURE AND THOSE IN REFS. /6/
AND /7/ WERE USED FOR THE RE-NORMALIZATION OF THE ABOVE DATA
AND FOR THE EVALUATION IN THE HIGH ENERGY REGION. THUS
OBTAINED CROSS SECTION WAS UNFOLDED BY CONSIDERING THE
EXPERIMENTAL RESOLUTION OF 0.054 NSEC/M/5/ BELOW 4.4 MEV.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4, 51-90, 91 INELASTIC SCATTERING
THE DATA FOR EACH LEVEL WERE CONSTRUCTED FROM THE EVALUATIONS
FOR EACH CR ISOTOPE AS FOLLOWS:
MT LEVEL ENERGY(MEV) CR-50 CR-52 CR-53 CR-54
G.S. 0.0
51 0.5640 51
52 0.7833 51
53 0.8349 51
54 1.0063 52
55 1.2895 53
56 1.4341 51
57 1.5366 54
58 1.8237 52
59 1.8814 52
60 1.9736 55
61 2.1724 56
62 2.2330 57
63 2.3208 58
64 2.3696 52
65 2.4531 59
66 2.6195 53
67 2.6470 53
68 2.6570 60
69 2.7677 54
70 2.7720 61
71 2.8266 62
72 2.8294 54
73 2.9245 53
74 2.9648 55
75 2.9930 63
76 3.0739 55
77 3.1138 56
78 3.1600 56
79 3.1611 54
80 3.1617 57
81 3.3247 55
82 3.4152 58
83 3.4722 59
84 3.6158 60
85 3.7000 61
86 3.7717 62
87 3.9460 63
88 4.0154 64
89 4.5630 65
90 4.6270 66
91 3.0500 91 91 91 91
MT=16 (N,2N)
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR CR ISOTOPES
SO AS TO REPRODUCE THE EXPERIMENTAL DATA OF FREHAUT/8/.
MT=22 (N,NA)
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR CR ISOTOPES.
MT=28 (N,NP)
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR CR ISOTOPES.
MT=102 CAPTURE
CALCULATED WITH THE CASTHY CODE/9/ AND NORMALIZED TO 10 MB AT
50 KEV. Q-VALUE IS A WEIGHTED AVERAGE VALUE OF ISOTOPE Q
VALUES.
MT=103 (N,P)
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR CR ISOTOPES.
MT=107 (N,A)
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR CR ISOTOPES
SO AS TO REPRODUCE THE EXPERIMENTAL DATA OF PAULSEN/10/.
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH THE CASTHY CODE/9/.
MT=51-90
CALCULATED WITH THE CASTHY CODE.
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=102 (BELOW 2.5 MEV)
FROM ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 2.5 MEV)
EVALUATED BASED ON THE EXPERIMENTAL DATA OF MORGAN/11/. BELOW
4.75 MEV, THE FINE STRUCTURES IN INELASTIC SCATTERING WERE
CONSIDERED.
MT=4 (BELOW 2.5 MEV)
CALCULATED FROM INELASTIC SCATTERING CROSS SECTIONS AND
GAMMA-RAY BRANCHING RATIOS OF ISOTOPES.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3, 4, 102
ASSUMED TO BE ISOTROPIC.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3
CALCULATED WITH THE GNASH CODE/12/.
MT=102
CALCULATED WITH THE CASTHY IN THE THERMAL ENERGY REGION
AND WITH GNASH ABOVE 100 KEV.
REFERENCES
1) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
2) YAMAMURO N.: JAERI-M 90-006 (1990).
3) EVALUATED NUCLEAR STRUCTURAL DATA FILE, BNL/NNDC.
4) HOLDEN N.E., MARTIN R.L. AND BARNES I.L. : PURE & APPL.
CHEM. 56, 675 (1984).
5) CIERJACKS S. ET AL. : KFK-1000 (1968).
6) FOSTER JR. D.G. ET AL. : PHYS. REV. C 3, 576 (1971).
7) PEREY F.G. : EXFOR DATA NO.10342 (1973).
8) FREHAUT J. ET AL. : 1980 BNL CONF. 399 (1980).
9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
10) PAULSEN A. : NUCL. SCI. ENG. 78, 377 (1981).
11) MORGAN G.L. ET AL. : ORNL/TM-5098 (1976).
12) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).