23-V - 51
23-V - 51 KHI EVAL-AUG88 T.WATANABE
DIST-SEP89 REV2-MAR94
----JENDL-3.2 MATERIAL 2328
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 JENDL-2 MODIFIED BY T.WATANABE
(KAWASAKI HEAVY INDUSTRIES, LTD.)
94-03 MODIFICATION FOR JENDL FUSION FILE WAS MADE BY S.CHIBA
GAMMA-RAY PRODUCTION DATA EVALUATED BY T.ASAMI(DATA ENG.)
COMPILED BY S.CHIBA AND T.NAKAGAWA(NDC/JAERI)
**** MODIFIED PARTS FOR JENDL-3.2 *******************************
(3,2) TO KEEP THE TOTAL CROSS CROSS
SECTION THE SAME AS JENDL-3.1.
(3,16) BELOW 15 MEV TAKEN FROM JENDL FUSION FILE
(3,4),(3,22),(3,28),(3,51-65),(3,91) TAKEN FROM JENDL FUSION FILE
(4,16),(4,22),(4,28),(4,51-65),(4,91)TAKEN FROM JENDL FUSION FILE
(5,16),(5,22),(5,28),(5,91) TAKEN FROM JENDL FUSION FILE
(12,51-64),(12,102),(12,103),(12,107) NEW EVALUATION
(13,3) NEW EVALUATION
(14,3),(14,51-64),(14,102),(14,103),(14,107) NEW EVALUATION
(15,3),(15,102),(15,103),(15,107) NEW EVALUATION
******************************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF MAR. 1994)
EVALUATED AND COMILED BY S. CHIBA (NDC/JAERI)
DATA WERE TAKEN FROM JENDL-3.1 EXCEPT FOR THE FOLLOWING:
- THE DISCRETE AND CONTINUUM INELASTIC SCATTERING CROSS
SECTIONS WERE CALCULATED WITH CASTHY2Y AND DWUCKY IN
SINCROS-II SYSTEM/2/.
- ANGULAR DISTRIBUTIONS OF DISCRETE INELASTICS WERE ALSO
CALCULATED WITH CASTHY2Y AND DWUCKY.
- THRESHOLD REACTION CROSS SECTIONS (MT=16, 22, 28) WERE
REPLACED WITH THOSE CALCULATED BY EGNASH2 IN THE
SINCROS-II. ABOVE 15 MEV, THE (N,2N) CROSS SECTION IS THE
SAME AS JENDL-3.1.
- ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED
BY THOSE CALCULATED BY EGNASH2. THE DDX'S OF THE CONTI-
NUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMATICS
/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
MT=151 RESONANCE PARAMETERS : 1.0E-5 EV - 100 KEV
RESOLVED RESONANCES FOR MLBW FORMULA:
PARAMETERS WERE EVALUATED BASED ON EXPERIMENTAL DATA
/5,6,7,8/ AND MODIFIED TO REPRODUCE EXPERIMENTAL TOTAL
CROSS SECTIONS. NEGATIVE ENERGY LEVELS WERE ADDED TO
REPRODUCE 2200 M/S TOTAL AND CAPTURE CROSS SECTIONS.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/SEC RES. INTEG.
ELASTIC 4.83 B -
CAPTURE 4.90 B 2.56 B
TOTAL 9.73 B -
MF=3 NEUTRON CROSS SECTIONS : ABOVE 100 KEV
FOR JENDL-3.1, TOTAL, ELASTIC, INELASTIC AND CAPTURE CROSS
SECTIONS WERE CALCULATED WITH OPTICAL AND STATISTICAL MODEL.
DIRECT INELASTIC REACTION CROSS SECTIONS WERE EVALUATED WITH
DWBA METHOD /9/ AND ADDED TO COMPOUND PROCESSES.
THE SPHERICAL OPTICAL POTENTIAL PARAMETERS WERE EVALUATED
TO REPRODUCE EXPERIMENTAL TOTAL CROSS SECTIONS /10,11,12/.
V = 50.71-0.4793*EN MEV R0= 1.227 FM A0= 0.663 FM
WS= 5.307-0.1911*EN MEV RS= 1.370 FM B = 0.394 FM
VSO= 6.560 MEV RSO=0.046 FM ASO=0.535 FM
OPTICAL AND STATISTICAL MODEL CALCULATION WAS PERFORMED
WITH CASTHY CODE /13/.
FOR JENDL-3.2, CROSS SECTIONS FOR (N,2N), (N,NP), (N,NA) AND
INELASTIC SCATTERING WERE ADOPTED FROM JENDL FUSION FILE.
THE CALCULATION WAS MADE WITH SINCROS-II CODE SYSTEM/2/ BY
ADOPTING WALTER-GUSS OMP MODIFIED BY YAMAMURO/2/ FOR
NEUTRONS, LEMOS OMP MODIFIED BY ARTHUR AND YOUNG/14/ FOR
ALPHA, LOHR-HAEBERLI/15/ FOR DEUTERON, BECHETTI-GREENLEES
/16/ FOR TRITON AND HE-3. LEVEL DENSITY PARAMETERS USED ARE:
V-52 9.0 (1/MEV)
V-51 8.6
V-50 8.6
TI-51 9.8
TI-50 8.6
SC-48 DEFAULT IN SINCROS-II
SC-47 DEFAULT IN SINCROS-II
MT=1 TOTAL
100 KEV -2 MEV: BASED ON THE EXPERIMENTAL DATA /11,12/ FOR
NATURAL V.
ABOVE 2 MEV: CALCULATED
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4,51-65,91 INELASTIC SCATTERING
ADOPTED FROM JENDL FUSION FILE.
THE LEVEL SCHEME TAKEN FROM REF./17/:
NO. ENERGY(MEV) SPIN-PARITY BETA
G.S 0.0 7/2-
1 0.3201 5/2-
2 0.9270 3/2- 0.250
3 1.6089 11/2- 0.250
4 1.8131 9/2- 0.250
5 2.4108 3/2-
6 2.5474 1/2+
7 2.6774 3/2+
8 2.6996 15/2-
9 2.79 9/2-
10 3.0836 5/2-
11 3.15 3/2-
12 3.1951 3/2-
13 3.2148 3/2-
14 3.2640 5/2-
15 3.2800 5/2-
CONTINUUM LEVELS ASSUMED ABOVE 3.28 MEV
MT=16 (N,2N)
TAKEN FROM JENDL FUSION FILE.
BELOW 15 MEV: SINCROS-II CALCULATION
ABOVE 15 MEV: GUIDED BY EXPERIMENTAL DATA /18/.
MT=22,28 (N,NA), (N,NP)
DATA FOR JENDL FUSION FILE WERE ADOPTED, WHICH WERE
CALCULATED WITH SINCROS-II.
MT=102 CAPTURE
STATISTICAL MODEL CALCULATION WITH CASTHY CODE /13/ WAS
PERFORMED. THE CAPTURE CROSS SECTION WAS NORMALIZED TO THE
EXPERIMENTAL DATA OF DUDEY+ /19/ AT 0.5 MEV 2.63 MB.
MT=103 (N,P)
GUIDED BY EXPERIMENTAL DATA /20,21/.
MT=104,105 (N,D), (N,HE-3)
JENDL-2 EVALUATED DATA /22/ WERE ADOPTED.
MT=107 (N,ALPHA)
GUIDED BY EXPERIMENTAL DATA /22,23,24,25/.
MT=251 MU-BAR
CALCULATED FROM THE DATA IN MF=4.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 CALCULATED WITH OPTICAL MODEL.
MT=51-65
TAKEN FROM JENDL FUSION FILE FOR WHICH THE CALCULATION WAS
MADE WITH HAUSER-FESHBACH FORMULA (CASTHY) AND DWBA (DWUCK4).
MT=16,22,28,91
TAKEN FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91
TAKEN FROM JENDL FUSION FILE.
MF=12 PHOTON PRODUCTION MULTIPLICITIES (UP TO 3.34494 MEV)
MT=51-64
MULTIPLICITIES WERE CALCULATED WITH EGNASH2/2/.
MT=102
FROM ENERGY BALANCE.
MT=103, 107
CALCULATED WITH THE EGNASH2 CODE/2/.
MF=13 PHOTON PRODUCTION CROSS SECTIONS (ABOVE 3.34494 MEV)
MT=3
CALCULATED WITH THE EGNASH2 CODE/2/.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3,51-64,102,103,107
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3, 102, 103, 107
CALCULATED WITH THE EGNASH2 CODE/2/. CAPTURE GAMMA SPECTRUM
AT THERMAL ENERGY WAS CALCULATED WITH CASTHY/6/.
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