20-CA- 0 DEC EVAL-MAR87 M.HATCHYA(DATA ENG. CO.)
DIST-SEP89 REV2-APR94
----JENDL-3.2 MATERIAL 2000
-----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)
90-06 MF=3,MT=251 AND AWR'S OF MF=4 WERE MODIFIED.
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 (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
ALL CROSS SECTIONS EXCEPT (3,1), (3,16), (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), (13,4)
(15,102), (15,103), (15,107)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF JAN. 1994)
EVALUATED BY K.KOSAKO (NEDAC) AND S.CHIBA (NDC/JAERI)
COMPILED BY K.KOSAKO.
- NATURAL CA DATA WERE CONSTRUCTED FROM DATA FOR ISOTOPES.
- 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 ANGULAR 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.
THE DATA WERE CONSTRUCTED FROM THE EVALUATED RESONANCE
PARAMETERS FOR EACH CA ISOTOPE EXCEPT FOR CA-46, CONSIDERING
THEIR ABUNDANCES IN THE CA ELEMENT/5/.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 3.0193
CAPTURE 0.4358 0.2262
TOTAL 3.4551
MF=3 NEUTRON CROSS SECTIONS
BELOW 500 KEV, BACKGROUND CROSS SECTION WAS GIVEN. THE TOTAL,
ELASTIC SCATTERING AND CAPTURE CROSS SECTIONS OF CA-42 IN THE
ENERGIES OF 300 TO 500 KEV AND OF CA-43 IN THE ENERGIES OF 40
TO 500 KEV, MULTIPLIED BY THEIR ABUNDANCES, WERE GIVEN AS THE
BACKGROUND CROSS SECTIONS FOR MT=1, 2 AND 102, RESPECTIVELY.
ABOVE 500 KEV, ALL THE CROSS SECTIONS EXCEPT FOR THE TOTAL WERE
CONSTRUCTED FROM THE EVALUATED ONES FOR STABLE ISOTOPES.
MT=1 TOTAL
THE DATA IN THE ENERGIES ABOVE 500 KEV WERE EVALUATED BASED ON
MAINLY THE EXPERIMENTAL ONES OF/6, 7/ BY FOLLOWING THEIR FINE
STRUCTURES.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4, 51-84, 91 INELASTIC SCATTERING
TAKEN FROM JENDL FUSION FILE WHICH WAS CONSTRUCTED FROM THOSE
OF CA ISOTOPES AS FOLLOWS:
MT ENERGY(MEV) CA-40 CA-42 CA-43 CA-44 CA-46 CA-48
51 0.3728 51
52 0.5934 52
53 0.9903 53
54 1.157 51
55 1.346 54 51
56 1.5246 51
57 1.6778 55
58 1.8373 52 52
59 1.9018 56
60 1.9314 57,58
61 2.2831 53
62 2.4231 53 52
63 2.5747 53
64 2.6565 54
65 2.7523 54
66 2.9739 54
67 3.0226 55 55
68 3.1893 55
69 3.2539 56 56
70 3.300 57 57,58
71 3.3521 51 59
72 3.391 58,59
73 3.614 60 56,57
74 3.7369 52
75 3.8317 58 51
76 3.9045 53
77 4.2842 52
78 4.4915 54
79 5.2129 55
80 5.2488 56
81 5.2788 57
82 5.6142 58
83 5.6296 59
84 5.9033 60
91 1.957 91 91 91 91 91 91
MT=16, 22, 28, 102, 103, 107, 111
(N,2N), (N,NA), (N,NP), CAPTURE, (N,P), (N,A) AND (N,2P)
CONSTRUCTED FROM THE EVALUATED DATA FOR CA ISOTOPES. THE DATA
FOR MT=103, 107 AND 111 ARE THE SAME AS JENDL-3.1. THOSE OF
MT=22 AND 28 WERE MAINLY TAKEN FROM JENDL FUSION FILE. THE
CAPTURE CROSS SECTION ABOVE 3 MEV WAS LARGELY CHANGED FROM
JENDL-3.1 BRCAUSE OF CA-40.
MT=251 MU-BAR
CALCULATED WITH THE OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH THE CASTHY CODE/8/.
MT=51-84
TAKEN FROM JENDL FUSION FILE.
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=102 (BELOW 4 MEV)
CALCULATED FROM ENERGY BALANCE.
MT=103, 107 (BELOW 4 MEV)
CALCULATED WITH THE GNASH CODE/9/.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 4 MEV)
CALCULATED WITH THE GNASH CODE/9/.
MT=4 (BELOW 4 MEV)
CALCULATED FROM THE INELASTIC SCATTRING CROSS SECTIONS AND THE
TRANSITION PROBABILITIES OF ISOTOPES.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3, 4, 102, 103, 107
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3, 103, 107
CALCULATED WITH THE GNASH CODE/9/.
MT=102
ASSUMED TO BE THE SAME AS THOSE OF CA-40 WHICH WERE CALCULATED
WITH CASTHY BELOW 10 KEV AND WITH GNASH ABOVE 200 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) CIERJACKS S. ET AL. : KFK-1000 (1968).
7) FOSTER JR. D.G. ET AL. : PHYS. REV. C3, 576 (1971).
8) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
9) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).