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76-Os- 0 FEI EVAL-JAN90 NIKOLAEV M.N. DIST-JAN09 20090105 ----JEFF-311 MATERIAL 7600 -----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 + Corrections ** ** ** ****************************************************************** ***************************** JEFF-3.0 *********************** DATA TAKEN FROM :- BROND-2.2 (DIST-OCT91) 19/02/2002: Decay scheme in MF12 modified by A. Hogenbirk (NRG Petten) ****************************************************************** 76-OS- 0 ***************************************************************** CONTENT OF THE FILE: MF = 1 GENERAL INFORMATION: MT = 451 COMMENTS ON EVALUATIONS, REFERENCES AND DICTIONARY. RESULTS OF EVALUATION FULFILLED BY NIKOLAEV M.N. (MF = 1-5, 9) AND ZABRODSKAYA S.V. (MF = 12, 14, 15) ARE GIVEN. DATA COMPILED AND CHECKED BY SAVOSKINA G.V. DESCRIPTION IS WRITTEN DOWN BY NIKOLAEV M.N. 0.0253 EV CROSS SECTIONS: RADIATIVE CAPTURE OS-184 3002.+-150.BARN RADIATIVE CAPTURE OS-186 79.+-13. BARN RADIATIVE CAPTURE OS-187 319.+-10. BARN RADIATIVE CAPTURE OS-188 4.8+-0.5 BARN RADIATIVE CAPTURE OS-189 25.4+-4. BARN RADIATIVE CAPTURE OS-190 13.1+-0.3 BARN RADIATIVE CAPTURE OS-192 1.93+-0.1 BARN RADIATIVE CAPTURE OS-NAT 15.9+-0.4 BARN ELASTIC SCATTERING OS-184 108. BARN ELASTIC SCATTERING OS-186 14.2+-5. BARN ELASTIC SCATTERING OS-187 10.9+-6. BARN ELASTIC SCATTERING OS-188 7.6+-0.6 BARN ELASTIC SCATTERING OS-189 15.3+-1.0 BARN ELASTIC SCATTERING OS-190 15.9+-0.9 BARN ELASTIC SCATTERING OS-192 17.9+-0.6 BARN ELASTIC SCATTERING OS-NAT 15.4+-0.4 BARN MF = 2 RESONANCE REGION: MT = 151 ONLY RESOLVED RESONANCE REGION IS DESCRIBED FOR EVERY OSMIUM ISOTOPE. PARAMETERS ONLY S-RESONANCE ARE GIVEN. AVERAGE RESONANCE PARAMETERS NOT GIVEN. LOW ENERGY BOUNDARY OF RRR IS 10-5 EV FOR EVERY ISOTOPE. PARAMETERS OF BOUND LEVEL ARE SPECIFIED FOR EVERY ISOTOPE TO OBTAIN THE EXPERIMENTAL CROSS SECTIONS VALUE AT 0.0253 EV. PARAMETERS OF SEVERAL FICTITIOUS RESONANCES ARE GIVEN FOR ENERGIES GREATER THAN UPPER BOUNDARY OF RRR FOR TAKING INTO ACCOUNT UNRESOLVED RESONANCE CONTRIBUTION IN RRR. --------------------------------------------- ! TOTAL ! UPPER ! NUMBER OF ISOTOPE! NUMBER OF ! BOUNDARY, ! ARTIFICIAL ! RESONANCES ! EV ! RESONANCES --------------------------------------------- OS-184 1 160 - OS-186 133 3360 5 OS-187 182 990 5 OS-188 107 5000 5 OS-189 27 77 5 OS-190 7 150 4 OS-192 4 150 1 --------------------------------------------- MF = 3 NEUTRON CROSS-SECTIONS: IN THE REGION FROM 10-5 EV TO 77 EV ALL CROSS SECTIONS ARE FULLY DETERMINED BY RESONANCE PARAMETERS LISTED IN MF=2. IN THE FILE MF=3 ALL CROSS SECTIONS IN THIS REGION PUT EQUAL TO ZERO. ABOVE THE 77 EV CONTRIBUTION OF OS-189 IS TAKEN INTO ACCOUNT IN THE FILE MF=3. ABOVE 150 EV CONTRIBUTIONS OF OS-190 AND OS-192 ARE TAKEN INTO ACCOUNT ALSO. ABOVE 990 EV AND TO 5000 EV CONTRIBUTION OF OS-187 IS TAKEN INTO ACCOUNT ALSO. THESE CONTRIBUTIONS WERE CALCULATED WITH THE HELP OF EVPAR CODE [1] ON THE BASIS OF AVERAGE RESONANCE PARAMETERS. ABOUT DETERMINATION OF CROSS SECTIONS ABOVE 5000 EV SEE BELOW. MT = 1 TOTAL CROSS SECTION FROM 5 KEV TO 100 KEV WAS CALCULATED ON THE BASIS OF AVERAGE PARAMETERS. ABOVE 100 KEV - FROM THE EYE GUIDE CURVE FROM [2]. MT = 2 ELASTIC SCATTERING CROSS SECTION ABOVE 5 KEV IS EQUAL TO DIFFERENCE BETWEEN TOTAL CROSS SECTION AND SUMMARIZED NONELASTIC CROSS SECTION. MT = 4 INELASTIC SCATTERING CROSS SECTION IS THE SUM OF MT = 51-67 AND MT = 91. MT = 16 CROSS SECTION OF (N,2N) REACTION WAS CALCULATED BY TNG CODE [3] FOR EVERY ABUNDANT ISOTOPE. FOR OS-184, OS-186 AND OS-192 PARAMETERS OF CALCULATION WERE FITTED FOR AGREEMENT WITH EXPERIMENTAL DATA. FOR OS-187 PARAMETERS OF OS-189 WERE USED. FOR OS-190 PARAMETERS OF OS-192 WERE USED. ABOVE THE THRESHOLD OF (N,3N) REACTION COMPETITION OF THIS REACTION WAS TAKEN INTO ACCOUNT. MT = 17 CROSS SECTION OF (N,3N) REACTION CALCULATED BY MULTIPLYING OF SUMMARIZED (N,2N) AND (N,3N) CROSS SECTION CALCULATED BY TNG CODE ON THE PROBABILITY OF EMISSION OF THIRD NEUTRON CALCULATED BY NEVA CODE [4] MT = 51-67 LEVEL EXCITATION CROSS SECTION WERE CALCULATED BY TNG CODE WITH THE NEXT LEVEL PARAMETERS MT ISOTOPE EN,KEV SPIN,PARITY 51 189 31 9/2- 52 189 36 1/2- 53 189 69 5/2- 54 189 95 3/2- 55 188 155 2+ 56 190 187 2+ 57 192 206 2+ 58 189 217 7/2- 59 189 219 7/2- 60 189 234 3/2- 61 189 276 5/2- 62 189 439 5/2- 63 188 478 4+ 64 192 489 2+ 65 190 548 4+ 66 192 580 4+ 67 192 690 3+ INELASTIC SCATTERING ON THE LIGHT ISOTOPES WITH LOW ABUNDANCE WAS TAKEN INTO ACCOUNT BY CORRESPONDING INCREASING OS-188 ABUNDANCE WHEN CROSS SECTIONS FOR NATURAL OSMIUM WAS CALCULATED. MT = 91 CONTINUUM INELASTIC CROSS SECTION CALCULATED ON THE BASIS OF STATISTICAL MODEL. BELOW THE THRESHOLD OF (N,3N) REACTION THIS CROSS SECTION CALCULATED BY TNG CODE. ABOVE THIS THRESHOLD CONTINUUM INELASTIC CROSS SECTION IS THE DIFFERENCE BETWEEN SUM OF CROSS SECTIONS MT = 4 + 16 + 17 + 102 + 103 + 107 CALCULATED BY TNG CODE AND SUM ADOPTED CROSS SECTIONS OF (N,2N), (N,3N), (N,GAMMA), (N,P) AND (N,ALFA). MT = 102 ISOTOPE CAPTURE CROSS SECTIONS FROM 5 KEV TO 1 MEV ADOPTED AS IN THE EYE GUIDE CURVES IN REF.[2] (FOR OS-190 AND OS-192 IRREGULARITIES ON THESE CURVES WERE SMOOTHED). CROSS SECTION FOR NATURAL OSMIUM WAS THEN CALCULATED. ABOVE 1 MEV FOR NATURAL OSMIUM THE PLATINUM RADIATIVE CAPTURE CROSS SECTION WAS ADOPTED AFTER RENORMALIZATION ON EVALUATED OSMIUM CROSS SECTION AT 1 MEV. (IN REF.[2] CROSS SECTION CURVES FOR OS-186, OS-187, OS-188 ARE SHARPLY INCREASED ON THE BASIS OF DATA OF REF.[5]. SO ANOMALOUS BEHAVIOR OF CROSS SECTIONS FOR ALL MEASURED ISOTOPES LEAD TO DOUBT IN THIS DATA). MT = 103, 107 (N,P) AND (N,ALFA) CROSS SECTIONS WERE CALCULATED BY TNG CODE WITH FITTING OF PARAMETERS OF CALCULATION FOR AGREEMENT WITH EXPERIMENTAL DATA. MT = 251, 252, 253 ARE CALCULATED ON THE BASIS OF MF = 4, MT = 2 DATA. MF = 4 ANGULAR DISTRIBUTIONS: MT = 2 ELASTIC SCATTERING ANGULAR DISTRIBUTION ACCEPTED AS THOSE FOR PLATINUM (ENDF/B-4 DATA). MT = 16, 17, 51-67, 91 (N,2N), (N,3N) AND INELASTIC SCATTERING NEUTRON ANGULAR DISTRIBUTIONS ACCEPTED AS ISOTROPIC IN THE LAB SYSTEM. MF = 5 ENERGY DISTRIBUTIONS: MT = 16, 17, 91 CONTINUOUS ENERGY DISTRIBUTIONS (N,2N), (N,3N) AND INELASTIC SCATTERING NEUTRONS ARE CALCULATED BY THE NEVA CODE [8] IN THE FRAME OF EVAPORATION MODEL. EVAPORATION TEMPERATURES WERE ESTIMATED ACCORDING TO GILBERT-CAMERON PRESCRIPTION. COMPETITION FROM THE RADIATIVE CHANNEL WAS NOT TAKEN INTO ACCOUNT. PRECOMPOUND EMISSION WAS TAKEN INTO ACCOUNT APPROXIMATELY. MF = 12 MULTIPLICITIES OF RADIATIVE TRANSITIONS. MT = 16, 17 MULTIPLICITIES OF CONTINUOUS ENERGY SPECTRA PHOTONS EMITTED IN (N,2N) AND (N,3N) REACTIONS IS ADOPTED AS FOR IRIDIUM BECAUSE RESULTS OF CALCULATIONS OF THESE SPECTRA BY TNG CODE FOR OSMIUM AND IRIDIUM WERE FINDED VERY CLOSE ONE TO ANOTHER. MT = 51-67 FOR EACH OF THIS REACTIONS LINE PHOTON SPECTRUM ARE GIVEN. PHOTON LINES WERE DETERMINED OR BY TRANSITIONS ON THE UNDERLYING LEVELS OR IN THE CASE OF INTERNAL CONVERSION BY CORRESPONDING ROENTGEN. OPTION L0=1 IS USED. MT = 91 PHOTON SPECTRA FOR INELASTIC SCATTERING WITH CONTINUOUS NEUTRON SPECTRA WERE ALSO ADOPTED CONTINUOUS. THIS PHOTON SPECTRA WERE WEIGHTED FOR AVERAGE ISOTOPE SPECTRA. THE LAST WAS CALCULATED FOR THE MAIN OSMIUM ISOTOPES BY TNG CODE. MT = 102 CONTINUOUS RADIATIVE CAPTURE PHOTON SPECTRA WERE ADOPTED. THESE SPECTRA AND MULTIPLICITIES WAS TAKEN BY AVERAGING OF CONTRIBUTIONS OF ODD AND EVEN OSMIUM ISOTOPES CALCULATED BY TNG CODE. MT = 103, 107 SPECTRA AND MULTIPLICITIES OF PHOTONS EMITTED IN (N,P) AND (N,ALFA) REACTIONS WERE CALCULATED BY TNG CODE. MF = 14 PHOTON ANGULAR DISTRIBUTIONS: MT = 16, 17, 51-67, 91, 102, 103, 107 ALL PHOTON ANGULAR DISTRIBUTIONS WERE TAKEN ISOTROPIC IN LAB. SYSTEM. MF = 15 CONTINUOUS PHOTON SPECTRA. MT = 16, 17, 51-67, 91, 102, 103, 107 SEE COMMENTS TO MF = 12. REFERENCES 1. MANTUROV G.N. ET AL. VANT "YADERNYE CONSTANTY" ISSUE 1(50),P.50. MOSCOW, 1983. 2. NEUTRON CROSS SECTIONS. V2. NEUTRON CROSS SECTIONS CURVES. V.MCLANE, C.L.DUNFORD, P.F.ROSE. NNDC BNL, ACADEMIC PRESS 1988. 3. SHIBATA K., FU C.Y. ORNL/TM-10093, 1986. 4. NIKOLAEV M.N. AND GILFANOVA O. NEVA - CODE FOR CALCULATION OF SPECTRA CONSEQUENTLY EVAPORATED NEUTRONS. FEI, 1988. UNPUBLISHED. 5. WINTERS ET.AL. PHYS.REV.C.21, P.563 (1980). ************************ C O N T E N T S ************************Back |