12-MG- 0 DEC,NEDAC EVAL-MAR87 M.HATCHYA(DEC),T.ASAMI(NEDAC)
DIST-SEP89 REV2-NOV93
----JENDL-3.2 MATERIAL 1200
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE FOR JENDL-3.
87-03 COMPILED BY T.ASAMI.
93-11 JENDL-3.2.
GAMMA-PRODUCTION DATA MODIFIED BY T.ASAMI(DATA ENG.)
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(12,102) BELOW 3 MEV
(13,4) BELOW 3 MEV
(14,4) NEW
(15,102) MODIFIED AT 1.0E-5 AND 0.0253 EV
***********************************************************
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 520 KEV. THE DATA ARE CONSTRUCTED
FROM THE EVALUATED RESONANCE PARAMETERS FOR MG-24, -25 AND -26,
CONSIDERING THEIR ABUNDANCES IN THE MG ELEMENT/1/.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 3.53
CAPTURE 0.063 0.0366
TOTAL 3.59
MF=3 NEUTRON CROSS SECTIONS
BELOW 520 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN.
ABOVE 520 KEV, THE TOTAL AND PARTIAL CROSS SECTIONS WERE GIVEN
POINTWISE.
ALL THE CROSS-SECTION DATA WERE CONSTRUCTED FROM THE EVALUATED
ONES FOR THREE STABLE ISOTOPES OF MG CONSIDERING THEIR
ABUNDANCES IN THE MG ELEMENT,
MT=1 TOTAL
CONSTRUCTED FROM THE EVALUATED DATA FOR STABLE ISOTOPES OF MG.
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
CONSTRUCTED FROM THE EVALUATED DATA FOR STABLE ISOTOPES OF MG
AS FOLLOWS:
MT LEVEL ENERGY(MEV) MG-24 MG-25 MG-26
0.0
51 0.5851 51
52 0.9748 52
53 1.3686 51
54 1.6118 53
55 1.8087 51
56 1.9647 54
57 2.5638 55
58 2.7377 56
59 2.8011 57
60 2.9384 52
61 3.4052 58
62 3.4137 59
63 3.5880 53
64 3.9078 60
65 3.9405 54
66 3.9707 61
67 4.0596 62
68 4.1200 52
69 4.2384 53
70 4.2770 63
71 4.3180 55
72 4.3320 56
73 4.3500 57
74 4.3594 64
75 4.7114 65
76 4.7220 66-67
77 4.8340 58
78 4.9000 59
79 4.9700 60
80 5.2361 54
81 5.2910 61
82 5.4740 62
83 5.6900 63
84 6.0103 55
85 6.4322 56
86 7.3479 57
87 7.5530 58
88 7.6162 59
89 7.7472 60
90 7.8120 61
LEVELS ABOVE 7.98 MEV WERE ASSUMED TO BE OVERLAPPING.
MT=16, 22, 28, 102, 103 AND 107 (N,2N), (N,NA), (N,NP),
(N,GAMMA), (N,P) AND (N,A)
CONSTRUCTED FROM THE EVALUATED DATA FOR THREE STABLE ISOTOPES
OF MG, TAKING ACCOUNT OF THEIR ABUNDANCES IN THE MG ELEMENT.
THE CALCULATED CAPTURE CROSS SECTIONS WERE NORMALIZED SO AS TO
REPRODUCE THE ELEMENT MG DATA OF 72 MB AT 500 KEV/2/.
MT=251 MU-BAR
CONSTRUCTED FROM THE EVALUATED DATA FOR STABLE ISOTOPES
OF MG, TAKING ACCOUNT OF THEIR ABUNDANCES IN THE MG ELEMENT.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CONSTRUCTED FROM THE EVALUATED DATA FOR STABLE ISOTOPES
OF MG, TAKING ACCOUNT OF THEIR ABUNDANCES IN THE MG ELEMENT.
MT=51-90, 91
CONSTRUCTED WITH THE EVALUATED DATA FOR STABLE ISOTOPES
OF MG, TAKING ACCOUNT OF THEIR ABUNDANCES IN THE MG ELEMENT.
MT=16, 22, 28
ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
CONSTRUCTED FROM THE EVALUATED DATA FOR STABLE ISOTOPES
OF MG, TAKING ACCOUNT OF THEIR ABUNDANCES IN THE MG ELEMENT.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=102
FROM ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 3 MEV)
CALCULATED WITH THE GNASH CODE/3/.
MT=4 (BELOW 3 MEV)
CALCULATED FROM INELASTIC CROSS SECTIONS AND TRANSITION
PROBABITIES OF MG ISOTOPES.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3, 4, 102
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3
CALCULATED WITH THE GNASH CODE/3/.
MT=102
CALCULATED WITH THE CASTHY CODE/4/ BELOW 0.0253 EV AND
WITH THE GNASH CODE/3/ AT HIGHER ENERGIES.
REFERENCES
1) HOLDEN N.E., MARTIN R.L. AND BARNES I.L. : PURE & APPL.
CHEM. 56, 675 (1984).
2) GRENIER ET AL. : CEA-N-2195 (1981).
3) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).
4) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).