88-Ra-223 TIT EVAL-AUG88 N.TAKAGI DIST-DEC21 20091124 ----JENDL-5 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. 21-11 revised by O.Iwamoto (MF8/MT4,16-18,37,102) added 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).