88-Ra-223 TIT EVAL-AUG88 N.TAKAGI
DIST-MAY10 20091124
----JENDL-4.0 MATERIAL 8825
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF
TECHNOLOGY, TIT)/1/
09-11 MF1 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 RESONANCE PARAMETERS
NO RESONANCE PARAMETERS WERE GIVEN.
2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 143.10 B -
ELASTIC 12.40 B -
FISSION 0.70 B 1.06 B
CAPTURE 130.00 B 435 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
BELOW 4 EV, CALCULATED AS SUM OF MT'S = 2, 18 AND 102.
ABOVE 4 EV, OPTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/6/. THE POTENTIAL PARAMETERS/7/ 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 4 EV, THE CONSTANT CROSS SECTION OF 12.4 BARNS WAS
ASSUMED, WHICH WAS THE SHAPE ELASTIC SCATTERING CROSS
SECTION CALCULATED WITH OPTICAL MODEL. ABOVE THIS ENERGY,
OPTICAL MODEL CALCULATION WAS ADOPTED.
MT=4,51-52,91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/6/. THE LEVEL SCHEME WAS TAKEN FROM REF./8/.
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 1/2 +
1 50.19 3/2 -
2 61.53 5/2 +
3 79.77 3/2 -
4 123.91 5/2 -
5 130.27 7/2 +
6 174.72 9/2 +
7 174.78 7/2 -
8 247.47 9/2 -
9 280.31 3/2 +
10 286.16 3/2 +
11 329.95 3/2 -
12 334.52 3/2 +
13 342.50 3/2 +
14 342.92 5/2 +
LEVELS ABOVE 369.43 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./9/.
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 0.7 BARN WAS TAKEN FROM
REF. 6 , AND 1/V FORM WAS ASSUMED BELOW 4 EV. ABOVE THIS
ENERGY, THE CONSTANT CROSS SECTION WAS ADOPTED.
MT=102 CAPTURE CROSS SECTION
MEASURED THERMAL CROSS SECTION OF 130 BARNS WAS TAKEN FROM
REF./10/, AND 1/V FORM WAS ASSUMED BELOW 4 EV.
ABOVE 4 EV, CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH
FUNCTION WAS ESTIMATED FROM GAMMA-GAMMA = 0.040 EV AND
LEVEL SPACING = 8 EV.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-64,91 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/11/.
REFERENCES
1) N.TAKAGI ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990).
2) G.Benedetti et al.: Nucl. Sci. Eng., 80, 379 (1982).
3) R.Waldo et al.: Phys. Rev., C23, 1113 (1981).
4) R.J.Tuttle: INDC(NDS)-107/G+Special, p.29 (1979).
5) T.Ohsawa: J. Nucl. Radiochem. Sci., 9, 19 (2008)
6) S.IGARASI: J.NUCL.SCI.TECHNOL.,12,67 (1975).
7) T.OHSAWA, M.OHTA: J. NUCL. SCI. TECHNOL., 18, 408 (1981).
8) C.MAPLES: NUCL. DATA SHEETS, 22, 243 (1977).
9) A.GILBERT, A.G.W.CAMERON: CAN. J. PHYS., 43, 1446 (1965).
10) S.F.MUGHABGHAB: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON
RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,
Z=61-100", ACADEMIC PRESS (1984).
11) A.B.SMITH ET AL.: ANL/NDM-50 (1979).