IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 7.61860+ 4 1.84356+ 2 1 0 0 17686 1451 1 0.00000+ 0 0.00000+ 0 0 0 0 67686 1451 2 1.00000+ 0 2.00000+ 7 0 0 10 937686 1451 3 0.00000+ 0 0.00000+ 0 0 0 39 77686 1451 4 76-Os-186 FEI EVAL-JUN92 NIKOLAEV M.N. 7686 1451 5 SEE REF. MT=451 1401937686 1451 6 ----FOND-2 MATERIAL 7686 7686 1451 7 -----INCIDENT NEUTRON ACTIVATION DATA 7686 1451 8 ------ENDF-6 FORMAT 7686 1451 9 7686 1451 10 ***************************************************************** 7686 1451 11 7686 1451 12 RESULTS OF EVALUATION FULFILLED BY NIKOLAEV M.N. 7686 1451 13 DATA ARE COMPILED AND CHECKED BY SAVOSKINA G.V. 7686 1451 14 --------------------------------------------------- 7686 1451 15 * 0.0253 EV CROSS SECTIONS: * 7686 1451 16 * RADIATIVE CAPTURE OS-186 79.+-13. BARN * 7686 1451 17 --------------------------------------------------- 7686 1451 18 7686 1451 19 COMMENTS TO CONTENT: 7686 1451 20 7686 1451 21 MF=3 - CROSS-SECTIONS. 7686 1451 22 -------------- 7686 1451 23 MT= 16- (N,2N) CROSS SECTION BASAED ON THRESHOLD 8.27 MEV 7686 1451 24 AND DATA AT 14.7 MEV 2.0 B. 7686 1451 25 7686 1451 26 MF=8 - RADIONUCLIDE PRODUCTION DATA 7686 1451 27 ---------------------------- 7686 1451 28 MT= 16 - OS-185 PRODUCED: 7686 1451 29 OS-185 (EC, GAM; T1/2=94 D) 7686 1451 30 MT=103 - THE NEXT NUCLIDES ARE PRODUCED: 7686 1451 31 RE-186G (BETA-, EC, GAM; T1/2=90.64 H) 7686 1451 32 RE-186M (IG; T1/2=200 000 Y) 7686 1451 33 7686 1451 34 MF=10 - RADIONUCLIDE PRODUCTION CROSS SECTIONS 7686 1451 35 -------------------------------------- 7686 1451 36 MT =103 - CROSS SECTION OF PRODUCTION OF RE-186G 7686 1451 37 BASED ON EXPERIMENTAL DATA. 7686 1451 38 CROSS SECTION OF PRODUCTION OF RE 186M 7686 1451 39 ADOPTED TO BE EQUAL ONE TENTH OF PREVIOUS. 7686 1451 40 EVALUATION IS BASED ON THE DATA FROM "NEUTR.XS,V.2.BNL,1988".7686 1451 41 ************************************************************* 7686 1451 42 7686 1451 43 1 451 50 07686 1451 44 3 16 6 07686 1451 45 3 103 6 07686 1451 46 3 203 6 07686 1451 47 8 16 2 07686 1451 48 8 103 3 07686 1451 49 10 103 11 07686 1451 50 7686 1 099999 7686 0 0 0 7.61860+ 4 1.84356+ 2 0 0 0 07686 3 16 1 -8.27070+ 6-8.27070+ 6 0 0 2 87686 3 16 2 2 2 8 5 7686 3 16 3 8.31556+ 6 0.00000+ 0 9.00000+ 6 1.00000+ 0 1.00000+ 7 1.80000+ 07686 3 16 4 1.20000+ 7 2.00000+ 0 1.47000+ 7 2.00000+ 0 1.60000+ 7 1.90000+ 07686 3 16 5 1.80000+ 7 1.40000+ 0 2.00000+ 7 7.00000- 1 7686 3 16 6 7686 3 099999 7.61860+ 4 1.84356+ 2 0 0 0 07686 3103 1 -2.94200+ 5-2.94200+ 5 0 0 2 97686 3103 2 4 2 9 5 7686 3103 3 2.95796+ 5 0.00000+ 0 4.46609+ 5 0.00000+ 0 4.00000+ 6 0.00000+ 07686 3103 4 7.00000+ 6 1.10000- 5 1.00000+ 7 1.43000- 4 1.47000+ 7 6.05000- 37686 3103 5 1.60000+ 7 1.43000- 2 1.80000+ 7 3.30000- 2 2.00000+ 7 4.40000- 27686 3103 6 7686 3 099999 7.61860+ 4 1.84356+ 2 0 0 0 07686 3203 1 -2.94200+ 5-4.44200+ 5 0 0 2 87686 3203 2 3 2 8 5 7686 3203 3 4.46609+ 5 0.00000+ 0 4.00000+ 6 0.00000+ 0 7.00000+ 6 1.00000- 67686 3203 4 1.00000+ 7 1.30000- 5 1.47000+ 7 5.50000- 4 1.60000+ 7 1.30000- 37686 3203 5 1.80000+ 7 3.00000- 3 2.00000+ 7 4.00000- 3 7686 3203 6 7686 3 099999 7686 0 0 0 7.61860+ 4 1.84356+ 2 0 0 1 17686 8 16 1 7.61850+ 4 0.00000+ 0 3 0 0 07686 8 16 2 7686 8 099999 7.61860+ 4 1.84356+ 2 0 0 1 17686 8103 1 7.51860+ 4 0.00000+ 0 10 0 0 07686 8103 2 7.51860+ 4 1.50000+ 5 10 3 0 07686 8103 3 7686 8 099999 7686 0 0 0 7.61860+ 4 1.84356+ 2 0 0 2 0768610103 1 -2.94200+ 5-2.94200+ 5 0 0 2 8768610103 2 3 2 8 5 768610103 3 2.95796+ 5 0.00000+ 0 4.00000+ 6 0.00000+ 0 7.00000+ 6 1.00000- 5768610103 4 1.00000+ 7 1.30000- 4 1.47000+ 7 5.50000- 3 1.60000+ 7 1.30000- 2768610103 5 1.80000+ 7 3.00000- 2 2.00000+ 7 4.00000- 2 768610103 6 -2.94200+ 5-4.44200+ 5 0 0 2 8768610103 7 3 2 8 5 768610103 8 4.46609+ 5 0.00000+ 0 4.00000+ 6 0.00000+ 0 7.00000+ 6 1.00000- 6768610103 9 1.00000+ 7 1.30000- 5 1.47000+ 7 5.50000- 4 1.60000+ 7 1.30000- 3768610103 10 1.80000+ 7 3.00000- 3 2.00000+ 7 4.00000- 3 768610103 11 768610 099999 7686 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0