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88-Ra-226 TIT EVAL-AUG88 N.TAKAGI DIST-JAN09 20090105 ----JEFF-311 MATERIAL 8834 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** JEFF-3.1 ************************* ** ** ** Original data taken from: JENDL-3.3 ** ** ** ****************************************************************** =========================================================== JENDL-3.2 data were automatically transformed to JENDL-3.3. Interpolation of spectra: 22 (unit base interpolation) (3,251) deleted, T-matrix of (4,2) deleted, and others. =========================================================== 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. *********************************************************** MF=1 GENERAL INFORMATION MT=451 COMMENT AND DICTIONARY MT=452 NUMBER OF NEUTRONS PER FISSION EVALUATED WITH SEMI EMPIRICAL FORMULA OF HOWERTON/2/. 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/3/. 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/4/. THE POTENTIAL PARAMETERS/5/ 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/4/. THE LEVEL SCHEME WAS TAKEN FROM REF./6/ 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./7/ 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./8/, AND 1/V FORM WAS ASSUMED BELOW 10 EV. FOR ENERGY REGION ABOVE 1 MEV, THE EVALUATION WAS BASED ON EXPERIMENTAL DATA /9,10,11,12/, 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. MT=251 MU-L CALCULATED WITH CASTHY. 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/13/. REFERENCES 1) TAKAGI N. ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990). 2) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977). 3) IVANOV R.N. ET AL.: AT. ENERG., 42, 505 (1977). 4) IGARASI S. AND FUKAFORI T.: JAERI 1321 (1991). 5) OHSAWA T., OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981). 6) ELLIS-AKOVALI Y.A.: NUCL. DATA SHEETS, 50, 229 (1987). 7) GILBERT A., CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965). 8) NAKAHARA H. ET AL.: J. INORG. NUCL. CHEM., 38, 203 (1976). 9) NOBLES R.A ET AL.: NUCL. PHYS., 5, 211 (1958). 10) BABENKO JU.A. ET AL.: YAD. FIZ., 7, 269 (1968). 11) ZHAGROV E.A. ET AL.: NUCL. PHYS., A213, 436 (1973). 12) NEMILOV YU.A. ET AL.: YAD. FIZ., 37, 819 (1983). 13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).Back |