40-ZR- 0 MAPI EVAL-NOV88 M.SASAKI (MAPI)
DIST-SEP89 REV2-APR94
----JENDL-3.2 MATERIAL 4000
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-11 COMPILED BY T.ASAMI (JAERI)
94-04 JENDL-3.2
RESONANCE PARAMS OF ZR-90 MODIFIED BY M.KAWAI(TOSHIBA).
GAMMA-RAY PRODUCTION DATA MODIFIED BY S.IGARASI(NEDAC).
OTHER MODIFICATIONS WERE ADOPTED FROM JENDL FUSION FILE.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(2,151) RESOLVED RESONANCE PARAMETERS OF ZR-90
ALL CROSS-SECTION DATA
MAINLY TAKEN FROM JENDL FUSION FILE
(4,16-91) TAKEN FROM JENDL FUSION FILE
(5,16-91) TAKEN FROM JENDL FUSION FILE
(12,102)
(13,3), (13,4), (13,103), (13,107)
(14,4), (14,103), (14,107)
(15,3), (15,102), (15,103), (15,107)
***********************************************************
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JENDL FUSION FILE /1/ (AS OF APR. 1994)
EVALUATED AND COMILED BY S.CHIBA (NDC/JAERI)
- THE DISCRETE INELASTIC SCATTERING CROSS SECTIONS AND
THEIR ANGULAR DISTRIBUTIONS WERE CALCULATED WITH CASTHY2Y
AND DWUCKY IN SINCROS-II SYSTEM/2/ FOR EACH ISOTOPE.
THE DATA OF NATURAL ZR WAS CONSTRUCTED FROM THESE ISOTOPE
DATA.
- OTHER REACTION CROSS SECTIONS, I.E., THE CONTINUUM
INELASTIC SCATTERING, (N,2N), (N,3N), (N,NA), (N,NP) AND
(N,ND) REACTION CROSS SECTIONS AND THEIR SECONDARY
NEUTRON ENERGY SPECTRA, AND (N,P), (N,D), (N,T), (N,HE3)
AND (N,A) CROSS SECTIONS WERE CALCULATED BY EGNASH2 IN
THE SINCROS-II FOR EACH ISOTOPE. THE DATA FOR NATURAL ZR
WAS CONSTRUCTED FROM THESE DATA.
- THE DDX'S OF THE CONTINUUM NEUTRONS WERE CALCULATED BY
KUMABE'S SYSTEMATICS /3/ USING F15TOB /1/. THE
PRECOMPOUND TO COMPOUND RATIO WAS TAKEN FROM THE EGNASH2
CALCULATION.
- OTHER DATA WERE TAKEN FROM JENDL-3.1.
- 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/4/.
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MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESONANCE PARAMETERS
RESOLVED RESONANCE PARAMETERS FOR MLBW FORMULA WERE GIVEN IN
THE ENERGY REGION FROM 1.0E-5 EV TO 171 KEV. UPPER BOUNDARIES
OF THE RESOLVED RESONANCE REGIONS ARE:
ZR-90: 171.0 KEV ZR-91: 30.16 KEV
ZR-92: 71.0 KEV ZR-94: 53.5 KEV
ZR-96: 100.0 KEV
UNRESOLVED RESONANCE PARAMETERS WERE GIVEN UP TO 100 KEV FOR
ZR-91, -92, -94. THE PARAMETERS WERE DETERMINED TO REPRODUCE
EVALUATED CAPTURE AND TOTAL CROSS SECTIONS. DESCRIPTION ON
EVALUATION IS GIVEN IN THE (1,451) OF EACH ISOTOPE. THE
ABUNDANCE DATA WERE TAKEN FROM REF./5/ TO BE 0.5145, 0.1122,
0.1715, 0.1738 AND 0.0280 FOR ZR-90, -91, -92, -94 AND -96,
RESPECTIVELY.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
TOTAL 6.6026
ELASTIC 6.4084
CAPTURE 0.1943 1.203
MF=3 NEUTRON CROSS SECTIONS
BELOW 100 KEV, NO BACKGROUND CROSS SECTION WAS GIVEN. BETWEEN
100 AND 171 KEV, CONTRIBUTIONS FROM ZR-91, 92, 94 AND 96 WERE
GIVEN AS BACKGROUND CROSS SECTIONS TO TOTAL, ELASTIC AND
CAPTURE.
FOR JENDL-3.2, THE ALL CROSS SECTION DATA EXCEPT FOR THE
TOTAL WERE ADOPTED FROM JENDL FUSION FILE. THE CALCULATION WAS
MADE WITH SINCROS-II SYSTEM/2/ BY ADOPTING WALTER-GUSS OMP
MODIFIED BY YAMAMURO/2/ FOR NEUTRONS, LEMOS OMP MODIFIED BY
ARTHUR AND YOUNG/6/ FOR ALPHA, THE SAME OMP'S AS THE PEGASUS
CALCULATION FOR OTHER CHARGED PARTICLES AND STANDARD LEVEL
DENSITY PARAMETERS OF SINCROS-II SYSTEM.
Q-VALUES OF THRESHOLD REACTIONS INCLUDING INELASTIC SCATTERING
WERE SLIGHTLY CHANGED FROM CORRECT VALUES TO CONSISTENT ONES
WITH THRESHOLD ENERGIES AND ATOMIC WEIGHT OF NATURAL ZR.
MT=1 TOTAL
MANY EXPERIMENTAL DATA ARE EXISTING. EVALUATED BASED ON THE
EXPERIMENTAL DATA.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4, 51-89, 91 INELASTIC SCATTERING
TAKEN FROM JENDL FUSION FILE. THE LEVEL SCHEME WAS TAKEN FROM
REF./4/. THE DATA FOR SOME LEVELS WERE LUMPED AS FOLLOWS:
MT LEVEL ENERGY(MEV) ZR-90 ZR-91 ZR-92 ZR-94 ZR-96
G.S. 0.0
51 0.918 51
52 0.934 51
53 1.205 51
54 1.300 52
55 1.383 52
56 1.466 52 53
57 1.495 53
58 1.593 51
59 1.671 54
60 1.750 52
61 1.761 51
62 1.847 54
63 1.882 53 53
64 2.042 54 55
65 2.067 55 53
66 2.131 55
67 2.150 56 56
68 2.170 56
69 2.187 52 57
70 2.201 58
71 2.225 54
72 2.260 59
73 2.288 60
74 2.319 53 61
75 2.329 57 57 55
76 2.356 62,63 58
77 2.395 64 58
78 2.439 56
79 2.486 59
80 2.507 59
81 2.604 60
82 2.698 61
83 2.739 54,55 60
84 2.819 61,62 62-64 57
85 2.903 63,64
86 2.958 65
87 3.039 66,67
88 3.078 56
89 3.309 57
91 2.395 91 91 91 91 91
MT=16, 22, 28, 103 AND 107 (N,2N), (N,NA), (N,NP), (N,P) AND
(N,A)
CONSTRUCTED FROM THE STATISTICAL-MODEL CALCULATIONS FOR
EACH ISOTOPE.
MT=102 CAPTURE
CONSTRUCTED FROM THE DATA OF EACH ISOTOPE, THEN MODIFIED BY
MULTIPLING AN ENERGY DEPENDENT FACTOR TO REPRODUCE THE
EXPERIMENTAL DATA OF STAVISSKIJ ET AL./7/ AND POENITZ /8/.
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 ELASTIC SCATTERING
CONSTRUCTED FROM THE STATISTICAL-MODEL/9/ CALCULATIONS
FOR EACH ISOTOPE.
MT=51-89 INELASTIC SCATTERING
TAKEN FROM JENDL FUSION FILE. CONSTRUCTED FROM THE DATA FOR
EACH ISOTOPE.
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE. DDX DATA IN MF6 WERE
APPROXIMATELY TRANSFORMED TO MF4 AND MF5.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE. DDX DATA IN MF6 WERE
APPROXIMATELY TRANSFORMED TO MF4 AND MF5.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=102
FROM ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 2 MEV)
CONSTRUCTED FROM THE DATA FOR 5 ISOTOPES, USING MULTIPLICITIES
CALCULATED WITH EGNASH /2/ AND CROSS SECTIONS.
MT=4 (BELOW 2 MEV)
CONSTRUCTED FROM LEVEL EXCITATION CROSS SECTIONS OF ISOTOPES
AND TRANSITION PROBABILITIES TAKEN FROM ENSDF.
MT=103, 107 (BELOW 2 MEV)
MADE FROM THE DATA FOR ISOTOPES CALCULATED WITH EGNASH.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3, 4, 102, 103, 107
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MF=3 (ABOVE 2 MEV)
CALCULATED WITH EGNASH.
MT=102
SPECTRA WERE CALCULATED WITH CASTHY FOR 5 ISOTOPES, REFERRING
TO THE COMPILATION OF GAMMA-RAY SPECTRA FOR THERMAL NEUTRON BY
LONE ET AL. /10/ , AT 1.0E-5, 2.53E-2, 1.0, 1.0E+2, 1.0E+3,
1.0E+5, 5.0E+5, 1.0E+6, 1.5E+6 AND 2.0E+6 EV. PRIMARY
TRANSITIONS WERE TAKEN INTO ACCOUNT FOR ZR-90, ZR-91 AND
ZR-94.
MF=103, 107 (BELOW 2 MEV)
CALCULATED WITH EGNASH.
REFERENCES
1) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).
2) YAMAMURO, N.: JAERI-M 90-006 (1990).
3) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).
4) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.
5) HOLDEN, N.E., MARTIN, R.L. AND BARNES, I.L. : PURE & APPL.
CHEM. 56, 675 (1984).
6) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).
7) STAVISSKIJ JU.JA. ET AL.: AT. ENERGIJA, 15, 323 (1963).
EXFOR 40679004.
8) POENITZ W.P.: ANL-83-4, P.239 (1982). EXFOR 12832003.
9) FU, C.Y. : ORNL/TM 7042 (1980).
10) LONE M.A. ET AL.: AT. DATA AND NUCL. DATA TABLES, 26, 511
(1981).