74-W -183
74-W -183 KHI,NEDAC EVAL-MAR87 T.WATANABE(KHI), T.ASAMI(NEDAC)
DIST-SEP89 REV2-JAN94
----JENDL-3.2 MATERIAL 7434
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE FOR JENDL-3.
94-01 JENDL-3.2.
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.
(4,16-91), (5,16-91)
THESE DATA WERE TAKEN FROM JENDL FUSION FILE.
***********************************************************
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JENDL FUSION FILE /1/ (AS OF JAN. 1994)
EVALUATED BY K.KOSAKO (NEDAC) AND S.CHIBA (NDC/JAERI)
COMPILED BY K.KOSAKO.
DATA WERE TAKEN FROM JENDL-3.1 EXCEPT FOR THE FOLLOWING:
- THE INELASTIC SCATTERING CROSS SECTIONS TO COTINUUM
(MT=91) WAS 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.
- 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/.
-------------------------------------------------------------
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 2.2 KEV. PARAMETERS WERE EVALUATED BY
EXAMINING BOTH THE EXPERIMENTAL DATA/5,6,7/ AND THE RECOMMENDED
DATA OF BNL/8/. FOR UNKNOWN RADIATIVE WIDTH, AN AVERAGE VALUE
OF 55 MILLI-EV WAS ASSUMED. PARAMETERS FOR A NEGATIVE
RESONANCE WERE SELECTED SO THAT THE 2200 M/S CROSS SECTION FOR
CAPTURE REPRODUCED GAVE A RECOMMENDED VALUE OF 10.2 BARNS/8/
AND GAVE A GOOD FIT TO THE EXPERIMENTAL DATA FOR TOTAL CROSS
SECTIONS AROUND THERMAL ENERGIES. THE SCATTERING RADIUS WAS
ASSUMED TO BE 7.3 FM. CALCULATED 2200 M/SEC CROSS SECTIONS AND
RESONANCE INTEGRALS ARE AS FOLLOWS:
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 2.38
CAPTURE 10.11 335.
TOTAL 12.49
MF=3 NEUTRON CROSS SECTIONS
BELOW 2.2 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN AND ALL
THE CROSS-SECTION DATA ARE REPRODUCED FROM THE EVALUATED
RESONANCE PARAMETERS WITH MLBW FORMULA.
FOR JENDL-3.1, ABOVE 2.2 KEV, THE TOTAL AND PARTIAL CROSS
SECTIONS WERE GIVEN MAINLY BASED ON THE THEORETICAL CALCULA-
TIONS. 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/9/ AND ECIS
/10/. THE SPHERICAL 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/11/.
FOR JENDL-3.2, ALL CROSS SECTION DATA EXCEPT FOR THE TOTAL,
ELASTIC SCATTERING AND CAPTURE 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 NEUTRON,
PEREY OMP /12/ FOR PROTON, LEMOS OMP MODIFIED BY ARTHUR AND
YOUNG/13/ FOR ALPHA, LOHR-HAEBERLI OMP/14/ FOR DEUTERON,
BECCHETTII-GREENLEES OMP/15/ FOR TRITON AND HE-3, AND STANDARD
LEVEL DENSITY PARAMETERS OF SINCROS-II SYSTEM.
MT=1 TOTAL
CALCULATED WITH THE COMBINED PROGRAM OF THE ECIS AND CASTHY
CODES. ALMOST THE SAME AS JENDL-3.1.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4, 51-60, 91 INELASTIC SCATTERING
THE DATA OF MT=51 TO 60 WERE CALCULATED WITH THE COMBINED
PROGRAM OF CASTHY /9/ AND ECIS/10/. THESE CROSS SECTIONS IN
JENDL-3.2 ARE THE SAME AS JENDL-3.1 EXCEPT THAT NEW CALCULATION
WAS MADE AT ADDITIONAL SEVERAL ENERGY POINTS. THE CROSS
SECTION OF MT=91 WAS CALCULATED WITH SINCROS-II FOR JENDL
FUSION FILE. THE LEVEL SCHEME WAS BASED ON REF./4/
CONTRIBUTIONS OF THE DIRECT PROCESS WERE CALCULATED FOR THE
LEVELS MARKED WITH '*'.
NO. MT ENERGY(MEV) SPIN-PARITY (DIRECT PROCESS)
G.S. 0.0 1/2 -
1 51 0.0465 3/2 - *
2 52 0.0991 5/2 - *
3 53 0.2070 7/2 - *
4 54 0.2088 3/2 -
5 55 0.2917 5/2 -
6 56 0.3089 9/2 - *
7 57 0.3095 11/2 +
8 58 0.4121 7/2 -
9 58 0.4530 7/2 -
10 59 0.4870 13/2 +
11 59 0.5330 1/2 +
12 60 0.5500 9/2 -
13 60 0.5953 9/2 -
14 60 0.6228 9/2 +
LEVELS ABOVE 0.624 MEV WERE ASSUMED TO BE OVERLAPPING. DATA OF
LEVELS 8-9, 10-11 AND 12-14 WERE LUMPED AS IS INDICATED IN THE
ABOVE TABLE. THE DIRECT INELASTIC SCATTERING CROSS SECTION WAS
CALCULATED ALSO FOR THE LEVELS AT 0.904, 0.935, 1.025, 1.485,
1.866, 2.127, 2.505, 2.912, 3.404, 4.0, 4.5, 5.0 AND 5.5 MEV,
AND ADDED TO MT=91.
MT=16, 17, 22, 28, 103, 104, 107
(N,2N), (N,3N), (N,NA), (N,NP), (N,P), (N,D), (N,A)
ADOPTED FROM JENDL FUSION FILE. THEORETICAL CALCULATION WAS
MADE WITH SINCROS-II. THE RESULTS WERE NORMALIZED TO
(N,2N) 2.150 B AT 14.7 MEV (SYSTEMATICS OF QAIM/16/),
(N,P) 0.0041 B AT 14.7 MEV MEASURED BY QAIM/16/,
(N,D)+(N,NP) 0.0013 B AT 14.7 MEV MEASURED BY QAIM/16/,
(N,A) 0.0018 B AT 14.7 MEV (SYSTEMATICS OF QAIM/16/).
MT=102 CAPTURE
CALCULATED WITH THE CASTHY CODE/9/ AND NORMALIZED TO 70+-9 MB
AT 500 KEV/17/. ABOVE 3 MEV, A STRAIGHT LINE IN LOG-LOG SCALE
WAS ADOPTED ASSUMING 1.0 MB AT 14 MEV FOR JENDL-3.2.
MT=251 MU-BAR
CALCULATED WITH THE OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
(MT=2, 51-60: THE SAME AS JENDL-3.1)
MT=2
CALCULATED WITH THE CASTHY CODE/9/.
MT=51-60
CALCULATED WITH THE COMBINED PROGRAM OF CASTHY/9/ AND
ECIS/10/ CODES.
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.
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) CAMARDA H.S. ET AL. : PHYS. REV. C8, 1813 (1973).
6) OHKUBO M. : JAERI-M 5624 (1974).
7) MACKLIN R.L. ET AL. : LA-9200-MS (1982).
8) MUGHABGHAB S.F. AND GARBER D.I. :"NEUTRON CROSS SECTIONS",
VOL. 2, PART B (1984).
9) IGARASI S. AND FUKAHORI T.: JAREI 1321 (1991).
10) RAYNAL J. : IAEA-SMR-9/8 P.281 (1972).
11) DELAROCHE J.F. ET AL. : 1979 KNOXVILLE CONF. 336 (1979).
12) PEREY F.G.: PHYS. REV., 131, 745 (1963).
13) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).
14) LOHR J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).
15) BECCHETTI F.D. JR. AND GREENLEES G.W.: "POLARIZATION
PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682
(1971).
16) QAIM,S.M. AND GRACA, C.: NUCL. PHYS., A242, 317 (1975).
17) VOIGNIER J. ET AL.: NUCL. SCI. ENG., 93, 43 (1986).