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90-Th-234 KINKI U. EVAL-JUL87 T.OHSAWA DIST-JAN09 20090105 ----JEFF-311 MATERIAL 9046 -----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 81-04 EVALUATION FOR JENDL-2 WAS MADE BY T. OHSAWA AND M. OHTA (KYUSHU UNIVERSITY: PRESENT ADDRESS OF OHSAWA IS KINKI UNIV.). DETAILS OF THE EVALUATION ARE DESCRIBED IN REF. /1/. 83-11 FISSION SPECTRUM WAS GIVEN. THE TOTAL, (N,2N) AND (N,3N) CROSS SECTIONS WERE MODIFIED. 87-07 JENDL-2 DATA WERE ADOPTED FOR JENDL-3. COMPILATION WAS MADE BY T.NAKAGAWA(JAERI). 94-06 JENDL-3.2. NU-P, NU-D AND NU-TOTAL WERE MODIFIED. COMPILED BY T.NAKAGAWA (NDC/JAERI) ***** MODIFIED PARTS FOR JENDL-3.2 ******************** (1,452), (1,455), (1,456) *********************************************************** MF=1 GENERAL INFORMATION MT=451 COMMENT AND DICTIONARY MT=452 NUMBER OF NEUTRONS PER FISSION SUM OF NU-P NAD NU-D. MT=455 DELAYED NEUTRONS PER FISSION AVERAGE VALUES OF SYSTEMATICS BY TUTTLE/2/, BENEDETTI ET AL./3/ AND WALDO ET AL./4/ DECAY CONSTANTS WERE ASSUMED TO BE THE SAME AS THOSE OF TH-232 EVALUATED BY BRADY AND ENGLAND/5/. MT=456 PROMPT NEUTRONS PER FISSION BASED ON THE SEMI-EMPIRICAL FORMULA OF HOWERTON /6/. MF=2 RESONANCE PARAMETERS MT=151 RESOLVED RESONANCES NO RESOLVED RESONANCES WERE ADOPTED, SINCE THERE WERE NO MEASUREMENTS MADE. THE CAPTURE CROSS SECTION AT 0.0253 EV /7/ WAS EXTRAPOLATED ON AN 1/V BASIS UP TO AN ENERGY OF 15 EV. THE FISSION CROSS SECTION AT 0.0253 EV IS LESS THAN 0.02 BARN /8/, THEREFORE IT WAS ASSUMED TO 0.0 BARN. CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEG.(BARNS) 2200-M/S RES. INTEG. TOTAL 14.75 - ELASTIC 13.0 - FISSION 0.0 0.26 CAPTURE 1.75 93.7 MF=3 NEUTRON CROSS SECTIONS MT=1 TOTAL CROSS SECTION OPTICAL MODEL CALCULATION WITH THE FOLLOWING PARAMETERS: V = 41.0 - 0.05*E (MEV), WS = 6.4 + 0.15*SQRT(E) (MEV), -- DER. WOODS-SAXON -- VSO= 7.0 (MEV), R0 = RSO = 1.31 (FM), RS = 1.38 (FM), A = B = ASO= 0.47 (FM). THESE PARAMETERS WERE TAKEN FROM THOSE FOR TH-232 /9/. MT=2 ELASTIC SCATTERING CROSS SECTION STATISTICAL AND OPTICAL MODEL CALCULATIONS USING THE CODE CASTHY /10/. MT=4,51-67,91 INELASTIC SCATTERING CROSS SECTION STATISTICAL AND OPTICAL MODEL CALCULATIONS. LEVEL SCHEME OF TH-234 (ESTIMATED FROM SYSTEMATICS) NO. ENERGY(MEV) SPIN-PARITY G.S. 0.0 0 + 1 0.048 2 + 2 0.160 4 + 3 0.336 6 + 4 0.576 8 + 5 0.730 0 + 6 0.767 2 + 7 0.785 2 + 8 0.853 4 + 9 0.882 1 - 10 0.889 4 + 11 0.942 3 - 12 0.987 6 + 13 1.050 5 - 14 1.053 6 + 15 1.073 8 + 16 1.206 7 + 17 1.277 8 + LEVELS ABOVE 1.06 MEV WERE ASSUMED TO BE OVERLAPPING. MT=16,17 (N,2N) AND (N,3N) CROSS SECTIONS CALCULATED BY MEANS OF THE EVAPORATION MODEL OF SEGEV AND CANER /11/. MT=18 FISSION CROSS SECTION FISSION PROBABILITY DEDUCED FROM DIRECT REACTION /12/ AND SYSTEMATICS OF BEHRENS /13/ WERE USED TO OBTAIN FISSION CROSS SECTION. MT=102 CAPTURE CROSS SECTION STATISTICAL AND OPTICAL MODEL CALCULATIONS WITH GAMMA-RAY STRENGTH FUNCTION OF 0.00791. MT=251 MU-BAR CALCULATED WITH OPTICAL MODEL. MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS MT=2,51-67,91 STATISTICAL AND OPTICAL MODEL CALCULATIONS. MT=16,17,18 ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM. MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS MT=16,17,91 EVAPORATION SPECTRA WERE GIVEN. MT=18 FISSION SPECTRUM WAS ESTIMATED FROM Z**2/A SYSTEMATICS OF SMITH ET AL. /14/. REFERENCES 1) OHSAWA T. AND OHTA M.: MEMOIRS FACULTY OF ENGINEERING, KYUSHU UNIV. 40, 149 (1980). 2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979), 3) BENEDETTI G. ET AL.: NUCL. SCI. ENG., 80, 379 (1982). 4) WALDO R. ET AL.: PHYS. REV., C23, 1113 (1981). 5) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129(1989). 6) HOWERTON R.J.: NUCL. SCI. ENG. 62, 438 (1977). 7) HARVEY B.G. AND PARSONS B.I.: PHYS. REV., 80, 1098 (1950). 8) OSBORNE C. AND COVEYOU I.: MON-P-178, P.10 (1948), AS CITED IN HUIZENGA J.R. ET AL. "THE ACTINIDE ELEMENTS", NATIONAL NUCLEAR ENERGY SERIESEM DIV. IV, VOL.14A (ED. SEABORG ET AL.) P.839 (1954). 9) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL. 18, 408 (1981). 10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991). 11) SEGEV M. AND CANER M.: ANN. NUCL. ENERGY 5, 239(1978). 12) BACK B.B. ET AL.: PHYS. REV. C13, 2374 (1974). 13) BEHRENS J.W.: UCID-17509-2 (1977); PHYS. REV. LETT. 39, 68 (1977). 14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).Back |