88-Ra-226 TIT EVAL-AUG88 N.TAKAGI
DIST-MAY10 20091124
----JENDL-4.0 MATERIAL 8834
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF
TECHNOLOGY, TIT)/1/
93-11 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,1), (3,18) BELOW 6 MEV.
***********************************************************
09-11 MF=1 was revised.
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
EVALUATED WITH SEMI EMPIRICAL FORMULAS/2,3,4/.
MT=456 Number of prompt fission neutrons
Evaluated with semi-empirical formula of Ohsawa/5/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV TO 1000 EV.
MULTI-LEVEL BREIT-WIGNER FORMULA WAS ADOPTED.
PARAMETERS WERE TAKEN FROM THOSE BY IVANOV/6/.
NO FISSION WIDTH WAS GIVEN FOR ALL THE RESONANCES.
AVERAGE GAM-G = 0.0258 EV
EFFECTIVE SCATTERING RADIUS = 9.60 FM
2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 22.58 B -
ELASTIC 9.80 B -
FISSION 7.0E-6 B 0.0119 B
CAPTURE 12.78 B 285.6 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE
PARAMETERS. ABOVE 1 KEV, OPTICAL MODEL CALCULATION WAS
MADE WITH CASTHY/7/. THE POTENTIAL PARAMETERS/8/ USED
ARE AS FOLLOWS,
V = 41.0 - 0.05*EN (MEV)
WS= 6.4 - 0.15*SQRT(EN) (MEV)
WV= 0 , VSO = 7.0 (MEV)
R = RSO = 1.31 , RS = 1.38 (FM)
A = ASO = 0.47 , B = 0.47 (FM)
MT=2 ELASTIC SCATTERING CROSS SECTION
BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE
PARAMETERS. ABOVE 1 KEV, OPTICAL MODEL CALCULATION WAS
ADOPTED.
MT=4,51-66,91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/7/. THE LEVEL SCHEME WAS TAKEN FROM REF./9/
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 0 +
1 67.67 2 +
2 211.54 4 +
3 253.73 1 -
4 321.54 3 -
5 416.60 6 +
6 446.20 5 -
7 626.90 7 -
8 650.00 0 +
9 669.40 8 +
10 824.60 0 +
11 857.90 9 -
12 873.70 2 +
13 960.00 10 +
14 1048.60 1 -
15 1070.50 2 -
16 1134.00 11 -
LEVELS ABOVE 1446 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./10/
MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS
CALCULATED WITH EVAPORATION MODEL.
MT=18 FISSION CROSS SECTION
MEASURED THERMAL CROSS SECTION OF 7 MICRO-BARN WAS TAKEN
FROM REF./11/, AND 1/V FORM WAS ASSUMED BELOW 10 EV. FOR
ENERGY REGION ABOVE 1 MEV, THE EVALUATION WAS BASED ON
EXPERIMENTAL DATA /12,13,14,15/, AND BETWEEN 15 EV AND
FISSION THRESHOLD, CROSS SECTION WAS ASSUMED TO BE THE
SAME AS THE VALUE AT 15 EV.
MT=102 CAPTURE CROSS SECTION
BELOW 1 KEV, CROSS SECTION WAS REPRESENTED WITH RESONANCE
PARAMETERS. ABOVE 1 KEV, IT WAS CALCULATED WITH CASTHY.
THE GAMMA-RAY STRENGTH FUNCTION WAS ESTIMATED FROM
GAMMA-GAMMA = 0.040 EV AND LEVEL SPACING = 30.3 EV.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-66,91 CALCULATED WITH OPTICAL MODEL.
MT=16,17,18,37 ISOTROPIC IN THE LAB SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,37,91 EVAPORATION SPECTRA
OBTAINED FROM LEVEL DENSITY PARAMETERS.
MT=18 MAXWELLIAN FISSION SPECTRUM.
TEMPERATURE WAS ESTIMATED FROM Z**2/A DEPENDENCE/16/.
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