20-Ca- 40
20-CA- 40 DEC EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)
DIST-SEP89 REV2-APR94
----JENDL-3.2 MATERIAL 2025
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE TO GIVE A FULL REVISION FOR JENDL-2
DATA.
87-03 COMPILED BY T.ASAMI(NEDAC)
94-04 JENDL-3.2.
GAMMA PRODCTION DATA MODIFIED BY T.ASAMI (DATA ENG.)
OTHER DATA WERE MAINLY ADOPTED FROM JENDL FUSION FILE.
COMPILED BY T.NAKAGAWA
***** MODIFIED PARTS FOR JENDL-3.2 ********************
ALL CROSS SECTIONS EXCEPT (3,103), (3,107) AND (3,111)
ALL ANGULAR DISTRIBUTIONS EXCEPT (4,2).
ALL ENERGY DISTRIBUTIONS.
(12,4), (12,102), (12,103), (12,107)
(13,3)
(15,102)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF NOV. 1993)
EVALUATED BY K.KOSAKO (NEDAC) AND S.CHIBA (NDC/JAERI)
COMPILED BY K.KOSAKO.
- THE TOTAL CROSS SECTION WAS MODIFIED IN THE ENERGY RANGE
ABOVE 10 MEV.
- 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,NA) AND (N,NP) REACTION CROSS SECTIONS
(MT=16, 22, 28) 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, CAPTURE, (N,P), (N,A) AND
(N,2P) 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 RESOLVED RESONANCE PARAMETERS
RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY
REGION FROM 1.0E-5 EV TO 500 KEV. PARAMETERS WERE TAKEN FROM
THE RECOMMENDED DATA OF BNL/5/ AND THE DATA FOR A NEGATIVE
RESONANCE WERE ADDED SO AS TO REPRODUCE THE RECOMMENDED THERMAL
CROSS SECTIONS FOR CAPTURE AND SCATTERNG/5/. THE SCATTERING
RADIUS WAS ASSUMED TO BE 3.6 FERMI. CALCULATED 2200 M/SEC
CROSS SECTIONS AND RESONANCE INTEGRALS ARE AS FOLLOWS:
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 3.022
CAPTURE 0.408 0.2125
TOTAL 3.430
MF=3 NEUTRON CROSS SECTIONS
BELOW 500 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN AND ALL
THE CROSS-SECTION DATA ARE REPRODUCED FROM THE EVALUATED
RESOLVED RESONANCE PARAMETERS WITH MLBW FORMULA.
FOR JENDL-3.2, ALL CROSS-SECTION DATA EXCEPT FOR THE CAPTURE,
(N,P) AND (N,A) 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 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
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY /10/. THE OPTICAL POTENTIAL PARAMETERS USED ARE:
V = 49.68, VSO = 7.12 (MEV)
WS = 7.76 - 0.5*EN, WV = 0 (MEV)
R = 1.17, RS = 1.09, RSO = 1.17 (FM)
A = 0.6, ASO = 0.6, B = 0.69 (FM)
ABOVE 10 MEV, MODIFIED TO REPRODUCE THE EXPERIMENTAL DATA/11,
12/.
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 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 '*',
USING DEFORMATION PARAMETERS COMPILED BY RAMAN ET AL./13/ AND
SPEAR/14/.
NO. ENERGY(MEV) SPIN-PARITY (DIRECT PROCESS)
0.0 0 +
1 3.3521 0 +
2 3.7369 3 - *
3 3.9045 2 + *
4 4.4915 5 - *
5 5.2129 0 +
6 5.2488 2 +
7 5.2788 4 + *
8 5.6142 4 - *
9 5.6296 2 +
10 5.9033 1 -
LEVELS ABOVE 5.903 MEV WERE ASSUMED TO BE OVERLAPPING. THE
DIRECT INELASTIC SCATTERING CROSS SECTIONS WERE CALCULATED FOR
THE LEVELS AT 6.026, 6.286, 6.583, 6.751, 7.114, 7.466, 7.659,
8.099 AND 8.424 MEV, AND ADDED TO MT=91.
MT=16 (N,2N)
THE CALCULATION FOR JENDL FUSION FILE WAS NOT ADOPTED. THIS
CROSS SECTION FOR JENDL-3.1 WAS EVALUATED ON THE BASIS OF
EXPERIMENTAL DATA OF ARNORD ET AL./15/ THE THRESHOLD ENERGY
WAS SLIGHTLY MODIFIED FOR JENDL-3.2.
MT=22, 28 (N,NA),(N,NP)
ADOPTED FROM JENDL FUSION FILE. THEORETICAL CALCULATION WAS
MADE WITH SINCROS-II.
MT=102 CAPTURE
CALCULATED WITH THE CASTHY CODE/16/ AND NORMALIZED TO 6.7 MB
AT 30 KEV. ABOVE 5.38 MEV, CROSS SECTIONS WERE DETERMINED
ON THE BASIS OF THE EXPERIMENTAL DATA/17,18/.
MT=103, 107, 111 (N,P), (N,A), (N,2P)
CALCULATED WITH THE GNASH CODE/19/ USING THE ABOVE MENTIONED
OPTICAL MODEL PARAMETERS. THE (N,P) CROSS SECTIONS WERE
NORMALIZED SO AS TO FIT TO THE EXPERIMENTAL DATA OF URECH AT
5.95 MEV/20/. THE (N,A) CROSS SECTIONS WERE NORMALIZED TO THE
EXPERIMENTAL DATA OF BARNES/21/ AT 14.1 MEV.
MT=251 MU-BAR
CALCULATED WITH THE OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH THE CASTHY CODE/10/.
MT=51-60
TAKEN FROM JENDL FUSION FILE CALCULATED WITH THE CASTHY AND
DWUCKY IN THE SINCROS-II SYSTEM.
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB
SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE, AND TRANSFORMED INTO THE LAB
SYSTEM.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=4 (UP TO 4.0 MEV)
MULTIPLICITY OF 1.0 WAS GIVEN.
MT=102 (UP TO 4.0 MEV)
FROM ENERGY BALANCE.
MT=103, 107
CALCULATED WITH THE GNASH CODE/19/.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 4.0 MEV)
CALCULATED WITH THE GNASH CODE/19/.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=4,3,102
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3, 102, 103, 107
CALCULATED WITH THE GNASH CODE/19/. CAPTURE GAMMA SPECTRAUM AT
THERMAL ENERGY WAS CALCULATED WITH CASTHY/10/.
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) MUGHAGHAB 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) FOSTOER D.G AND GLASGOW D.W.: PHYS. REV. C3, 576 (1971).
12) CAMARDA H.S. ET AL.: PHYS. REV. C34, 810 (1986).
13) RAMAN, S., ET AL.: ATOM. DATA AND NUCL. DATA TABLES 36, 1
(1987)
14) SPEAR, R.H.: ATOM. DATA AND NUCL. DATA TABLE, 42, 55 (1989).
15) ARNOLD D.W. : TAKEN FROM EXFOR (1965).
16) ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE)
17) BERGQVIST I. ET AL.: NUCL. PHYS. A231, 29 (1974).
18) BUDNAR M. ET AL.: INDC(YUG)-6 (1979).
19) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).
20) URECH S. : NUCL. PHYS. A111, 184 (1968).
21) BARNES J.W. ET AL.: J. INORG. NUCL. CHEM. 37, 399 (1975).