88-Ra-226 TIT EVAL-AUG88 N.TAKAGI DIST-DEC21 20091124 ----JENDL-5 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. 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 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/. 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) R.N.IVANOV ET AL.: AT. ENERG., 42, 505 (1977). 7) S.IGARASI AND T.FUKAFORI: JAERI 1321 (1991). 8) T.OHSAWA, M.OHTA: J. NUCL. SCI. TECHNOL., 18, 408 (1981). 9) Y.A.ELLIS-AKOVALI: NUCL. DATA SHEETS, 50, 229 (1987). 10) A.GILBERT, A.G.W.CAMERON: CAN. J. PHYS., 43, 1446 (1965). 11) H.NAKAHARA ET AL.: J. INORG. NUCL. CHEM., 38, 203 (1976). 12) R.A.NOBLES ET AL.: NUCL. PHYS., 5, 211 (1958). 13) Ju.A.BABENKO ET AL.: YAD. FIZ., 7, 269 (1968). 14) E.A.ZHAGROV ET AL.: NUCL. PHYS., A213, 436 (1973). 15) Yu.A.NEMILOV ET AL.: YAD. FIZ., 37, 819 (1983). 16) A.B.SMITH ET AL.: ANL/NDM-50 (1979).