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73-Ta-182 NEA RCOM-JUN82 SCIENTIFIC CO-ORDINATION GROUP DIST-JAN09 20090105 ----JEFF-311 MATERIAL 7331 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 ** ** ** ****************************************************************** ***************************** JEFF-3.1 ************************* ** ** ** Original data taken from: JEFF-3.0 ** ** ** ****************************************************************** ***************************** JEFF-3.0 *********************** DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92) ****************************************************************** * JEF-2 * * DATA WERE TAKEN FROM ENDF/B-IV (MAT=1127) * ****************************************************************** * 20-AUG-84: J-VALUES FOR UNRES.RES.PARAM. CORRECTED * 8-JAN-85: Q-VALUE FOR MT=107 CORRECTED ****************************************************************** AI EVAL-APR71 J.OTTER,C.DUNFORD,AND E.OTTEWITTE AI-AEC-12990 (1971) DIST-MAY74 EXTENDED TO 20 MEV FOR ENDF/B VERSION-IV * * * * * * * TANTALUM-182 ENDF/B MAT 1127, MAY 1971 (REF) AI-AEC-12990 THERMAL XSCX AND RESONANCE PARAMETERS EVALUATED BY JOHN OTTER. FAST CROSS SECTIONS EVALUATED BY CHARLES DUNFORD AND ERIC OTTEWITTE. FILE ASSEMBLY BY PHILIP ROSE. MF=1 MT=451. DESCRIPTIVE INFORMATION ATOMIC MASS/ MATTAUCH,THIELE,WAPSTRA. NUCL.PHYS. 67,1(65). MF=2 MT=151. RESONANCE PARAMETERS RESOLVED RESONANCES - E, 2*G*(GAMMA,N), AND GAMMA GAMMA WHERE KNOWN FROM NSE 33,16. UNKNOWN GAMMA GAMMA EQUAL TO AVERAGE OF KNOWN VALUES. J ASSIGNED IN PROPORTION TO 2*J+1. NEGATIVE ENERGY RESONANCE PARAMETERS FROM FIT TO TOTAL CROSS SECTIONS AT ONE AND THREE EV. CALCULATED 2200 M/S CROSS SECTIONS ARE CAPTURE=8249B, SCATTERING=31B, AND TOTAL=8280B. POTENTIAL SCATTERING ASSUMED SAME AS TA-181, = 8.3B. UNRESOLVED RESONANCE PARAMETERS ENERGY INDEPENDENT. DOBS AND GAMMA GAMMA FROM RESOLVED RESONANCE RANGE S0, S1, AND S2 SAME AS TA-181. D(J)/DOBS FROM AAEC/TM 392. RESONANCE INTEGRAL - CAPTURE (0.5EV-100KEV) = 1020B. THERE IS NO EXPERIMENTAL COMPARISON. MF=3 MT=1. TOTAL CROSS SECTION 2PLUS AND COMNUC CALCULATIONAL RESULTS WERE USED DIRECTLY. MF=3 MT=2. ELASTIC CROSS SECTION 2PLUS AND COMNUC CALCULATIONAL RESULTS WERE USED DIRECTLY. MF=3 MT=4. TOTAL INELASTIC CROSS SECTION EQUAL TO THE SUM OF THE LEVEL EXCITATION AND CONTINUUM XSCS. MF=3 MT=16. N-2N CROSS SECTION THE ADOPTED CROSS SECTION IS THE TA-181 N-2N CROSS SECTION SHIFTED IN ENERGY TO THE TA-182 THRESHHOLD. MF=3 MT=17. N-3N CROSS SECTION THE N-3N CROSS SECTION WAS OBTAINED BY SUBTRACTING THE N-2N AND INELASTIC CONTINUUM FROM THE NON-ELASTIC CROSS SECTION. MF=3 MT=51. INELASTIC EXCITATION (DIRECT AND COMPOUND NUCLEUS) TO THE 97 KEV LEVEL. CROSS SECTIONS CALCULATED BY THE COMPUTER PROGRAMS 2PLUS AND COMNUC HAVE BEEN ADOPTED WITHOUT CHANGE AT ENERGIES WELL ABOVE THE THRESHHOLD. SEEMINGLY UNPHYSICAL STRUCTURE CALCULATED BY THE COMNUC CODE WAS SMOOTHED OUT NEAR THE THRESHHOLD. MF=3 MT=52-58,91. INELASTIC EXCITATION (COMPOUND NUCLEUS ONLY) CALCULATION BY 2PLUS-COMNUC FOR 114, 173, 237, 270, 292, 315 AND 360 KEV LEVELS PLUS THE CONTINUUM. STRUCTURE IN THE 114 KEV LEVEL NEAR THRESHHOLD SMOOTHED OUT. STRUCTURE CAUSED BY COMPETITION FOR OPEN CHANNELS DUE TO 1ST LEVEL WEAKLY COUPLED AND 2ND LEVEL STRONGLY COUPLED TO THE GROUND STATE. MF=3 MT=102. N-GAMMA CROSS SECTION 2PLUS-COMNUC RESULTS USED TO 5 MEV. ABOVE 5 MEV THE THEORY OF V. BENZI AND G. REFFO WAS USED. REF CCDN-NW/10 ENEA DATA CENTER MF=3 MT=107. N-ALPHA CROSS SECTION SAME AS TA-181 (MAT 1126) MF=4 MT=2. ANGULAR DISTRIBUTION OF ELASTICALLY-SCATTERED NEUTS. TRANSFORMATION MATRIX CALCULATED FOR MASS 182. LEGENDRE COEFFICIENTS TAKEN DIRECTLY FROM 2PLUS-COMNUC RUNS. MF=4 MT=51-58,91. ANGULAR DISTRIBUTION OF NEUTRONS INELASTICALLY SCATTERED TO DISCRETE LEVELS. THE LEVEL DISTRIBUTIONS WERE MADE ISOTROPIC IN THE CM FRAME. THE CONTINUUM WAS MADE ISOTROPIC IN THE LAB FRAME. MF=5 MT=16,17. NUCLEAR TEMPERATURES - (N,2N),(N,3N) REACTIONS. TEMPERATURE OF FIRST EMITTED NEUTRON SAME AS FOR MT=91. TEMPERATURE OF SECOND AND THIRD EMITTED NEUTRONS DEDUCED BY CONSERVATION OF ENERGY, ASSUMING THE KINETIC ENERGY OF AN EMITTED NEUTRON IS 2*KT. MF=5 MT=91. NUCLEAR TEMPERATURE - INELASTIC CONTINUUM MAXWELLIAN DISTRIBUTION USED TO DESCRIBE NUCLEAR TEMPERATURE. LEVEL SPACING SAME AS TA-181 (MAT 1126). U SPECIFIED FOR TA-182 THRESHHOLDS.Back |