20-Ca- 46
20-CA- 46 MITSUI E.S.EVAL-APR80 M.HATCHYA
DIST-FEB84 REV2-NOV93
----JENDL-3.2 MATERIAL 2043
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
80-04 NEW EVALUATION WAS MADE BY M.HATCHYA (MITSUI).
83-11 ANG. DIST. WAS MODIFIED.
84-02 COMMENT WAS ADDED.
88-10 UNCHANGED FROM JENDL-2.
93-11 JENDL-3.2
DATA WERE MAINLY ADOPTED FROM JENDL FUSION FILE.
COMPILED BY T.NAKAGAWA
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,2), (3,4), (3,16), (3,17), (3,22), (3,28), (3,51-91)
ALL ANGULAR DISTRIBUTIONS EXCEPT FOR (4,2).
ALL ENERGY DISTRIBUTIONS.
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF NOV. 1993)
EVALUATED BY K.KOSAKO (NEDAC) AND S.CHIBA (NDC/JAERI)
COMPILED BY K.KOSAKO.
- 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.
- 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.
- THE TOTAL, CAPTURE, (N,P) AND (N,A) CROSS SECTIONS AND
ANG. DISTRIBUTIONS OF ELASTICALLY SCATTERED NEUTRONS 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/.
-------------------------------------------------------------
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 NO RESONANCE PARAMETERS
2200-M/SEC CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS
2200-M/SEC RES.INTEG.
ELASTIC 2.900 B -
CAPTURE 0.7400 B 0.339 B
TOTAL 3.640 B -
MF=3 NEUTRON CROSS SECTIONS
THERMAL REGION WAS ASSUMED BELOW 1.0 KEV. THE CAPTURE AND
ELASTIC SCATTERING CROSS SECTIONS WERE ASSUMED TO BE 0.74 BARNS
/5/ AND 2.9 BARNS AT 0.0253 EV, RESPECTIVELY. THE TOTAL CROSS
SECTION WAS CALCULATED AS A SUM OF THESE TWO.
FOR JENDL-3.2, ABOVE 1 KEV, ALL CROSS-SECTION DATA EXCEPT FOR
THE TOTAL, CAPTURE, (N,P) AND (N,A) CROSS SECTIONS 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 /6/ FOR PROTON, LEMOS OMP
MODIFIED BY ARTHUR AND YOUNG/7/ FOR ALPHA, LOHR-HAEBERLI OMP/8/
FOR DEUTERON, BECCHETTII-GREENLEES OMP/9/ FOR TRITON AND HE-3,
AND STANDARD LEVEL DENSITY PARAMETERS OF SINCROS-II SYSTEM.
MT=1 TOTAL CROSS SECTION
THE OPTICAL MODEL CALCULATION WITH CASTHY /10/ WAS ADOPTED.
OPTICAL POTENTIAL PARAMETERS WERE TAKEN FROM REF./11/.
V = 46.72 (MEV),
WS = 9.13 (MEV),
VSO= 5.37 (MEV),
R0 = RSO = 1.26 (FM),
RS = 1.39 (FM),
A = ASO= 0.76 (FM),
B = 0.40 (FM).
MT=2 ELASTIC SCATTERING CROSS SECTION
DERIVED BY SUBTRACTING PARTIAL CROSS SECTIONS FROM THE TOTAL
CROSS SECTION.
MT=4,51-53,91 INELASTIC SCATTERING CROSS SECTIONS
THE CROSS SECTIONS WERE TAKEN FROM JENDL FUSION FILE. THE
LEVEL SCHEME WAS BASED ON REF./4/ CONTRIBUTIONS OF THE
DIRECT PROCESS WERE CALCULATED FOR THE LEVELS MARKED WITH '*'
BY MEANS OF DWUCKY. DEFORMATION PARAMETERS WERE ADOPTED FROM
RAMAN ET AL./12/ AND SPEAR/13/.
NO. ENERGY(MEV) SPIN-PARITY (DIRECT PROCESS)
0.0 0 +
1 1.346 2 + *
2 2.4231 0 +
3 2.5747 4 +
4 2.9739 6 +
5 3.0226 2 +
6 3.6140 3 - *
7 3.6389 2 +
8 3.8597 4 +
LEVELS ABOVE 3.86 MEV WERE ASSUMED TO BE OVERLAPPING.
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.
MT=102 CAPTURE CROSS SECTION
CALCULATED WITH CASTHY /10/.
MT=103,107 (N,P) AND (N,ALPHA) CROSS SECTIONS
STATISTICAL AND PRE-EQUILIBRIUM MODEL CALCULATIONS USING THE
OPTICAL POTENTIAL PARAMETERS FOR THE TOTAL CROSS SECTION.
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
OPTICAL MODEL CALCULATION
MT=51-58
TAKEN FROM JENDL FUSION FILE. CALCULATED WITH THE CASTHY AND
DWUCKY IN THE SINCROS-II SYSTEM.
MT=16, 17, 22, 28, 91
TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB
SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 17, 22, 28, 91
TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB
SYSTEM.
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. ET AL.: NEUTRON CROSS SECTIONS, VOL. 1, PART A
(1981).
6) PEREY, F.G.: PHYS. REV., 131, 745 (1963).
7) ARTHUR, E.D. AND YOUNG, P.G.: LA-8626-MS (1980).
8) LOHR, J.M. AND HAEBERLI W.: NUCL. PHYS., A232, 381 (1974).
9) BECCHETTI, F.D. JR. AND GREENLEES G.W.: "POLARIZATION
PHENOMENA IN NUCL. REACTIONS," UNIV. WISCONSIN PRESS, P.682
(1971).
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
11) FU C.Y.: ATOMIC DATA AND NUCLEAR DATA TABLE 17, 127 (1976).
12) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1
(1987)
13) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).