82-PB- 0 JAERI EVAL-JUL87 M.MIZUMOTO
DIST-SEP89 REV2-JUN94
----JENDL-3.2 MATERIAL 8200
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEWLY EVALUATED FOR JENDL-3 BY M.MIZUMOTO (JAERI)
87-11 REVISION IS RECOMMENDED.
89-09 REVISION IS COMPLETED.
COMPILATION WAS MADE BY. T.NARITA AND T.FUKAHORI (JAERI)
94-06 JENDL-3.2.
RESONANCE PARAMETERS CORRECTED BY T.NAKAGAWA
DATA FOR MF=3,4,5 WERE ADOPTED FROM JENDL FUSION FILE
GAMMA-RAY PRODUCTION DATA MODIFIED BY K.SHIBATA(JAERI)
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,4), (3,16). (3,17), (3,22), (3,28), (3,51-91)
(4,16-91), (5,16-91)
THESE DATA WERE TAKEN FROM JENDL FUSION FILE.
(2,151) REICH-MOORE FORMULA ADOPTED FOR PB-204, 206 AND
208. UPPER BOUNDARIES OF RESONANCE REGIONS WERE
CHANGED.
(3,1) BELOW 1 MEV
(3,102)
(3,2) TO COMPANSATE THE ABOVE MODIFICATIONS
(12,102), (13,3), (13,4), (15,3), (15,102)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF OCT. 1993)
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 AND ANGULAR
DISTRIBUTIONS OF INELASTICALLY SCATTERED NEUTRONS (EXCEPT
CONTINUUM INELASTIC) WERE CALCULATED WITH CASTHY2Y AND
DWUCKY IN SINCROS-II SYSTEM/2/ INCLUDING CONTRIBUTIONS
FROM DIRECT REACTIONS.
- THE (N,2N), (N,3N), (N,NA) AND (N,NP) REACTION CROSS
SECTIONS (MT=16, 17, 22, 28) WERE CALCULATED BY EGNASH2
IN THE SINCROS-II. THE (N,2N) CROSS SECTION WAS
RENORMALIZED TO EXPERIMENTAL DATA.
- ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED
WITH 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
RESONANCE RANGES AND FORMULA
PB-204: 1.0E-5 EV TO 50 KEV, MLBW
PB-206: 1.0E-5 EV TO 500 KEV, REICH-MOORE
PB-207: 1.0E-5 EV TO 475 KEV, REICH-MOORE
PB-208: 1.0E-5 EV TO 1 MEV, REICH-MOORE
PARAMETERS WERE EVALUATED FROM THE FOLLOWING EXPERIMENTAL DATA
AND RECOMMENDATION BY MUGHABGHAB/5/.
PB-204: HOREN+84 /6/
PB-206: HOREN+79 /7/, MIZUMOTO+79 /8/
PB-207: HOREN+78 /9/
PB-208: HOREN+86 /10/
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.
2200 M/S RES. INTEG.
ELASTIC 11.073 B -
CAPTURE 0.174 B 0.143 B
TOTAL 11.248 B -
MF=3 NEUTRON CROSS SECTIONS
BELOW 1 MEV, BACKGROUND CROSS SECTIONS ARE GIVEN.
FOR JENDL-3.2, THE THRESHOLD REACTION CROSS SECTIONS WERE
ADOPTED FROM JENDL FUSION FILE. THEIR 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/11/ FOR ALPHA, THE SAME OMP'S AS THE PEGASUS CALCULATION
FOR OTHER CHARGED PARTICLES AND STANDARD LEVEL DENSITY
PARAMETERS OF SINCROS-II SYSTEM. DATA FOT NATURAL PB WERE
CONSTRUCTED FROM DATA FOR ISOTOPES.
MT=1 TOTAL
CROSS SECTIONS IN THE ENERGY RANGE FROM 1 TO 15 MEV WERE
OBTAINED BASED ON THE EXPERIMENTAL DATA OF SCHWARTZ+74 /12/.
ABOVE 15 MEV, CROSS SECTIONS WERE CALCULATED WITH AN OPTICAL AND
STATISTICAL MODEL CODE CASTHY /13/. THE OPTICAL POTENTIAL
PARAMETERS WERE OBTAINED BY FITTING AVERAGE TOTAL CROSS SECTION
OF NATURAL LEAD AS FOLLOWS,
V=47.0 - 0.250*E, WS = 2.30 + 0.41*E, VSO = 6.0 (MEV)
R0 = 1.25 , RS = 1.30 , RSO = 1.30 (FM)
A0 = 0.65 , B = 0.48 , AS0 = 0.689 (FM)
LEVEL DENSITY PARAMETERS WERE DETERMINED USING LOW-LYING
LEVEL DATA AND OBSERVED NEUTRON RESONANCE SPACING.
MT=2 ELASTIC SCATTERING
(TOTAL)-(ALL OTHER PARTIAL CROSS SECTIONS)
MT=4,51-90,91 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 ENERGY(MEV) PB-204 PB-206 PB-207 PB-208
51 0.5697 51
52 0.8031 51
53 0.8977 51 52
54 1.165 52
55 1.2739 52
56 1.3405 53 53
57 1.467 54
58 1.5631 54-56
59 1.6334 53
60 1.665 57
61 1.682 58 55
62 1.703 59 56
63 1.7619 60,61 57
64 1.9977 58
65 2.149 59
66 2.2002 60
67 2.315 61 54
68 2.379 62-64
69 2.424 65
70 2.6146 51
71 2.6232 55,56
72 2.703 57,58
73 3.1977 52
74 3.4751 53
75 3.7087 54
76 3.9198 55,56
77 3.961 57,58
78 4.037 59-61
79 4.0854 62
80 4.106 63,64
81 4.141 65,66
82 4.1804 67
83 4.2054 68
84 4.2295 69,70
85 4.2535 71
86 4.2624 72
87 4.296 73
91 1.817 91 91 91 91
MT=16, 17, 22, 28 (N,2N), (N,3N), (N,NA), (N,NP)
ADOPTED FROM JENDL FUSION FILE. THEORETICAL CALCULATION WAS
MADE WITH SINCROS-II. THE (N,2N) CROSS SECTION WAS ADJUSTED TO
REPRODUCE THE MEASURED ENARGY SPECTRA/14/ (FACTOR = 1.2). THE
DATA OF SIMAKOV ET AL. /15/ WERE ALSO TAKEN INTO CONSIDERATION.
MT=102 CAPTURE
CALCULATED WITH CASTHY /13/ FOR PB-204, PB-206 AND PB-207. FOR
PB-208, ESTIMATED FROM THE EXPERIMENTAL DATA. THE CAPTURE CROSS
SECTION OF NATURAL LEAD WAS CONSTRUCTED FROM THESE ISOTOPES.
Q-VALUE IS WEIGHTED AVERAGE OF Q-VALUES OF ISOTOPES.
MT=103, 107 (N,P), (N,A)
CALCULATED WITH GNASH /16/ FOR EACH ISOTOPE AND CONSTRUCTED
ACCORDING TO THEIR ABUNDANCES.
MT=251 MU-BAR
CALCULATED WITH CASTHY /13/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH CASTHY /13/.
MT=51-87
TAKEN FROM JENDL FUSION FILE WHICH WERE CONSTRUCTED FROM
ISOTOPE DATA CALCULATED WITH SINCROS-II(CASTHY AND DWUCKY).
MT=16,17,22,28,91
ADOPTED FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,22,28,91
ADOPTED FROM JENDL FUSION FILE.
MF=12 GAMMA-RAY MULTIPLICITY PRODUCED BY NEUTRON REACTIONS
MT=102 (BLELOW 1.8 MEV)
CALCULATED FROM ENERGY BALANCE.
MF=13 GAMMA-RAY PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 1.8 MEV)
CALCULATED WITH GNASH /16/ FOR EACH ISOTOPE AND CONSTRUCTED
ACCORDING TO THEIR ABUNDANCES.
MT=4 (BELOW 1.8 MEV)
CALCULATED FROM INELASTIC SCATTERING CROSS SECTIONS AND
TRANSITION PROBABILITIES OF ISOTOPES.
MF=14 ANGULAR DISTRIBUTIONS OF SECONDARY GAMMA-RAYS
MT=3, 4, 102 : ASSUMED ISOTROPIC.
MF=15 ENERGY DISTRIBUTION OF SECONDARY GAMMA-RAYS
MT=3 (ABOVE 1.8 MEV)
CALCULATED WITH GNASH /16/ FOR EACH ISOTOPE AND CONSTRUCTED
ACCORDING TO THEIR ABUNDANCES.
ABOVE 10 MEV, THE CALCULATED SPECTRA WERE MODIFIED SO AS TO
REPRODUCE THE MEASUREMENTS OF CHAPMAN ET AL./17/
MT=102 (BELOW 1.8 MEV)
CALCULATED WITH CASTHY/13/.
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) MUGHABGHAB S.F.: NEUTRON CROSS SECTIONS, VOL.1, PART B,
ACADEMIC PRESS (1984).
6) HOREN D.J. ET AL. : PHYS. REV. C29, 2126 (1984).
7) HOREN D.J. ET AL. : PHYS. REV. C20, 478 (1979).
8) MIZUMOTO M. ET AL. : PHYS. REV. C19 ,335 (1979).
9) HOREN D.J. ET AL. : PHYS. REV. C18, 722 (1978).
10) HOREN D. J. ET AL. : PHYS. REV. C34, 420 (1986).
11) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).
12) SCHWARTZ R.B. ET AL.: NBS-MONO-138 (1974), DATA IN EXFOR
(1971).
13) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
14) TAKAHASHI A. ET AL.: JAERI-M 86-080, 393 (1986).
15) SIMAKOV S.P. ET AL: WORKSHOP ON NUCL. DATA FOR FUSION REACTOR
TECHNOL., DEL MAR, MAR 3-6 (1993).
16) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).
17) CHAPMAN G.T. ET AL.: ORNL/TM-4822 (1975).