74-W - 0 KHI,NEDAC EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)
DIST-SEP89 REV2-JUN94
----JENDL-3.2 MATERIAL 7400
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE FOR JENDL-3.
87-03 COMPILED BY T.ASAMI.
89-08 MF/MT=15/102 MODIFIED.
94-06 JENDL-3.2.
GAMMA PRODUCTION DATA MODIFIED BY T.ASAMI(DATA ENG.).
OTHERS WERE MAINLY BASED ON JENDL FUSION FILE.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
ALL CROSS SECTIONS EXCEPT TOTAL
THE INELASTIC SCATTERING, (N,2N), (N,3N), (N,NP),
(N,NA), (N,P), (N,D) AND (N,A) CROSS SECTIONS WERE
TAKEN FROM JENDL FUSION FILE. FURTHER MODIFICATION
WAS MADE FOR THE INELASTIC SCATTERING AND CAPTURE
CROSS SECTIONS.
(4,16-28), (4,91), (5,16-91)
TAKEN FROM JENDL FUSION FILE.
(12,102) UP TO 400 KEV
(13,4) UP TO 400 KEV
(13,3), (15,3) ENERGY RANGE WAS CHANGED
(15,102)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF JAN. 1994)
EVALUATED BY K.KOSAKO (NEDAC) AND S.CHIBA (NDC/JAERI)
COMPILED BY K.KOSAKO.
- THE INELASTIC SCATTERING CROSS SECTIONS TO HIGH EXCITED
LEVELS WERE CALCULATED WITH CASTHY2Y AND DWUCKY IN
SINCROS-II SYSTEM/2/ INCLUDING CONTRIBUTIONS FROM DIRECT
REACTIONS.
- THE (N,2N), (N,3N), (N,NA), (N,NP), (N,P), (N,D) AND
(N,A) REACTION CROSS SECTIONS (MT=16, 17, 22, 28, 103,
104, 107) WERE CALCULATED BY EGNASH2 IN THE SINCROS-II.
- ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED
BY THOSE CALCULATED BY EGNASH2. THE DDX'S OF THE
CONTINUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMA-
TICS /3/ USING F15TOB /1/. THE PRECOMPOUND/COMPOUND
RATIO WAS CALCULATED BY THE SINCROS-II CODE SYSTEM.
- THE RESONANCE PARAMETERS, TOTAL AND CAPTURE CROSS
SECTIONS WERE TAKEN FROM JENDL3.1.
- 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/.
-------------------------------------------------------------
ALL THE DATA WERE CONSTRUCTED WITH THE EVALUATED ONES OF W-182,
-183, -184 AND -186, TAKING ACCOUNT OF THEIR ABUNDANCES IN THE
W ELEMENT. THE ABUNDANCE DATA WERE TAKEN FROM REF./5/ TO BE
0.263, 0.143, 0.3067 AND 0.286 FOR W-182, -183, -184 AND -186,
RESPECTIVELY. ALL THE DATA OF W-180 WERE IGNORED BECAUSE OF ITS
VERY LOW ABUNDANCE. THE ABUNDANCE OF 0.2643 WAS USED FOR W-182
SOMETIMES.
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 TAKEN FROM THE
EVALUATED DATA ON EACH STABLE ISOTOPE. THE ENERGY REGION WAS
TAKEN FROM 1.0E-5 EV TO 15 KEV. CALCULATED 2200 M/SEC CROSS
SECTIONS AND RESONANCE INTEGRALS ARE AS FOLLOWS:
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
TOTAL 23.224
ELASTIC 4.973
CAPTURE 18.251 317.5
MF=3 NEUTRON CROSS SECTIONS
BELOW 15 KEV, BACKGROUND CROSS SECTION WAS GIVEN.
FOR JENDL-3.1, ABOVE THE RESONANCE REGION, THE TOTAL AND
PARTIAL CROSS SECTIONS OF EACH ISOTOPE WERE MAINLY BASED ON
THEORETICAL CALCULATIONS. THE TOTAL, ELASTIC AND INELASTIC
SCATTERING, AND CAPTURE CROSS SECTIONS WERE CALCULATED WITH THE
COUPLED-CHANNEL MODEL AND THE SPHERICAL OPTICAL-STATISTICAL
MODEL. THE CALCULATIONS WERE PERFORMED WITH A COMBINED PROGRAM
OF CASTHY/6/ AND ECIS/7/. THE OPTICAL POTENTIAL PARAMETERS
USED ARE:
V = 48.83 - 0.0809*EN, VSO = 5.6 (MEV)
WS = 6.73 - 0.0536*EN, WV = 0 (MEV)
R = 1.168, RS = 1.268, RSO = 1.592 (FM)
A = 0.617, ASO = 0.664, B = 0.563 (FM)
THE DEFORMED POTENTIAL PARAMETERS WERE TAKEN FROM THE WORK OF
DELAROCHE/8/.
FOR JENDL-3.2, ALL CROSS SECTION DATA EXCEPT FOR THE TOTAL,
ELASTC SCATTERING AND CAPTURE WERE ADOPTED FROM JENDL FUSION
FILE. NEW THEORETICAL CALCULATION WAS MADE WITH SINCROS-II
SYSTEM/2/ BY ADOPTING WALTER-GUSS OMP MODIFIED BY YAMAMURO/2/
FOR NEUTRON, PEREY OMP /9/ FOR PROTON, LEMOS OMP MODIFIED BY
ARTHUR AND YOUNG/10/ FOR ALPHA, LOHR-HAEBERLI OMP/11/ FOR
DEUTERON, BECCHETTII-GREENLEES OMP/12/ FOR TRITON AND HE-3,
AND STANDARD LEVEL DENSITY PARAMETERS OF SINCROS-II SYSTEM.
MT=1 TOTAL
[SAME AS JENDL-3.1]
THE DATA WERE CONSTRUCTED FROM THOSE OF FOUR W ISOTOPES WHICH
WERE CALCULATED WITH THE OPTICAL MODEL.
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 ISOTOPES WERE CALCULATED WITH THE COMBINED PROGRAM
OF THE ECIS/7/ AND CASTHY /6/, AND SINCROS-II. THE DATA FOR
NATURAL W WERE CONSTRUCTED FROM THE CALCULATED VALUES FOR EACH
W ISOTOPE AS FOLLOWS:
MT LEVEL ENERGY(MEV) W-182 W-183 W-184 W-186
G.S. 0.0
51 0.0465 51
52 0.0991 52
53 0.1001 51
54 0.1112 51
55 0.1226 51
56 0.2070 53
57 0.2088 54
58 0.2917 55
59 0.3089 56
60 0.3095 57
61 0.3294 52
62 0.3641 52
63 0.3968 52
64 0.4121 58
65 0.4870 59
66 0.5500 60
67 0.6805 53
68 0.7377 53
69 0.7483 53
70 0.8088 54
71 0.8618 55
72 0.8820 56
73 0.9033 54
74 0.9526 57
75 1.0023 55
76 1.0059 56
77 1.0070 58
78 1.0316 59
79 1.0452 60
80 1.1214 57
81 1.1357 54
82 1.1445 55
83 1.1500 61
84 1.2213 58
85 1.2214 56
86 1.2840 62
87 1.2950 59
88 1.3221 60
89 1.3311 57
90 1.4428 58
THE OTHER INELASTIC SCATTERING CROSS SECTIONS WERE SUMMED UP
TO MT=91
MT=16, 17, 22, 28, 102, 103 AND 107
(N,2N), (N,3N), (N,NA), (N,NP), CAPTURE, (N,P) AND (N,A)
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR STABLE ISOTOPES OF
W. THE CALCULATED CAPTURE CROSS SECTION FOR EACH W ISOTOPE WAS
NORMALIZED SO AS TO REPRODUCE THE ELEMENT W DATA OF 60+-6 MB AT
500 KEV/13/.
MT=251 MU-BAR
CALCULATED FROM MF/MT=4/2.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
(MF=2, 51-90: THE SAME AS JENDL-3.1)
MT=2
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR STABLE ISOTOPES
OF W.
MT=51-90
CONSTRUCTED FROM THE EVALUATED DATA FOR FOUR STABLE ISOTOPES.
MT=16, 17, 22, 28, 91
TAKEN FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 17, 22, 28, 91
TAKEN FROM JENDL FUSION FILE.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=102 (BELOW 400 KEV)
CALCULATED FROM ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 400 KEV)
CALCULATED WITH THE GNASH CODE/14/.
MT=4 (UP TO 400 KEV)
CALCULATED FROM CROSS SECTIONS AND TRANSITION PROBABILITIES
FOR LEVELS UP TO 400 KEV.
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/14/.
MT=102
CALCULATED WITH THE GNASH CODE/14/ IN THE ENERGY RANGE ABOVE
10 KEV, AND WITH CASTHY/6/ BELOW 1 KEV.
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) IGARASI S. AND FUKAHORI T.: JAREI 1321 (1991).
7) RAYNAL J. : IAEA-SMR-9/8 P.281 (1972).
8) DELAROCHE J.F. ET AL. : 1979 KNOXVILLE CONF. 336 (1979).
9) PEREY F.G.: PHYS. REV., 131, 745 (1963).
10) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).
11) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).
12) BECCHETTI F.D. JR. AND GREENLEES G.W.: "POLARIZATION
PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682
(1971).
13) VOIGNIER J. ET AL.: NUCL. SCI. ENG., 93, 43 (1986).
14) YOUNG, P.G. AND ARTHUR, E.D. : LA-6947 (1977).