IAEA-NDS ENDF Download System, v-2008-07-22 0 0 0 0 3.00670+ 4 6.63522+ 1 1 0 0 23067 1451 1 0.00000+ 0 0.0 + 0 0 0 0 63067 1451 2 1.00000+ 0 2.0 + 7 0 0 10 913067 1451 3 0.0 + 0 0.0 + 0 0 0 33 73067 1451 4 30-Zn- 67 FEI EVAL-DEC89 NIKOLAEV M.N. 3067 1451 5 SEE REF.MT=451 DIST-OCT91 REV1-FEB92 9210033067 1451 6 ----FOND-2 MATERIAL 3067 3067 1451 7 -----INCIDENT NEUTRON ACTIVATION DATA 3067 1451 8 ------ENDF-6 FORMAT 3067 1451 9 3067 1451 10 ******************************************************************3067 1451 11 3067 1451 12 COMMENTS: 3067 1451 13 DATA ARE COMPILED AND TESTED BY G.V.SAVOSKINA. 3067 1451 14 MF=1 GENERAL INFORMATION 3067 1451 15 ------------------- 3067 1451 16 MT=451- DATA DESCRIPTION WAS MADE BY M.N.NIKOLAEV. 3067 1451 17 3067 1451 18 MF=3 REACTION CROSS SECTIONS. 3067 1451 19 ------------------------- 3067 1451 20 MT=22,28,103-ALL DATA ARE CALCULATED BY TNG CODE 3067 1451 21 WITH RENORMALIZATION ON THE EXPERIMENTAL 3067 1451 22 DATA WHEN POSSIBLE. 3067 1451 23 3067 1451 24 3067 1451 25 MF=8 RADIONUCLIDE PRODUCTION DATA 3067 1451 26 ----------------------------- 3067 1451 27 MT=22 ZN-67(N,N+ALF)NI-63 (100 Y,BETA-) 3067 1451 28 MT=28 ZN-67(N,N+P)CU-66 (5.1 M,BETA-,GAM) 3067 1451 29 MT=103 ZN-67(N,P)CU-67 (61.9 H,BETA-,GAM) 3067 1451 30 3067 1451 31 REFERENCES 3067 1451 32 ------------ 3067 1451 33 1.NEUTRON CROSS SECTIONS V.1 PART A,AP,1981 3067 1451 34 2.NEUTRON CROSS SECTIONS V.2,AP,1989 3067 1451 35 ---------------------------------------------------------------- 3067 1451 36 3067 1451 37 1 451 44 03067 1451 38 3 22 10 03067 1451 39 3 28 10 03067 1451 40 3 103 9 03067 1451 41 8 22 2 03067 1451 42 8 28 2 03067 1451 43 8 103 2 03067 1451 44 3067 1 099999 3067 0 0 0 3.00670+ 4 6.63522+ 1 0 0 0 03067 3 22 1 -4.79023+ 6-4.79023+ 6 0 0 1 213067 3 22 2 21 2 3067 3 22 3 4.86412+ 6 0.00000+ 0 5.00000+ 6 6.51695- 6 5.00000+ 6 6.51695- 63067 3 22 4 5.12500+ 6 1.52379- 5 5.25000+ 6 2.73193- 5 5.37500+ 6 4.36424- 53067 3 22 5 5.50000+ 6 6.52615- 5 5.62500+ 6 9.34337- 5 5.75000+ 6 1.29644- 43067 3 22 6 5.87500+ 6 1.75642- 4 6.00000+ 6 2.33477- 4 6.25000+ 6 3.56519- 43067 3 22 7 6.50000+ 6 5.22078- 4 6.75000+ 6 7.40610- 4 7.00000+ 6 1.02439- 33067 3 22 8 7.75000+ 6 1.50378- 3 8.50000+ 6 2.13371- 3 9.25000+ 6 2.94305- 33067 3 22 9 1.00000+ 7 3.96341- 3 1.50000+ 7 6.10544- 3 2.00000+ 7 8.04878- 33067 3 22 10 3067 3 099999 3.00670+ 4 6.63522+ 1 0 0 0 03067 3 28 1 -8.90880+ 6-8.90880+ 6 0 0 1 193067 3 28 2 19 2 3067 3 28 3 9.04621+ 6 0.00000+ 0 9.20000+ 6 1.00000- 4 9.40000+ 6 2.70000- 43067 3 28 4 9.50000+ 6 1.00000- 3 9.60000+ 6 1.80000- 3 9.70000+ 6 2.30000- 33067 3 28 5 9.80000+ 6 3.70000- 3 9.90000+ 6 6.00000- 3 1.00000+ 7 7.50000- 33067 3 28 6 1.02500+ 7 9.09000- 3 1.05000+ 7 1.10000- 2 1.07500+ 7 1.30000- 23067 3 28 7 1.10000+ 7 1.57000- 2 1.15000+ 7 2.20000- 2 1.20000+ 7 3.07000- 23067 3 28 8 1.30000+ 7 3.25000- 2 1.40000+ 7 3.40000- 2 1.70000+ 7 3.70000- 23067 3 28 9 2.00000+ 7 3.90000- 2 3067 3 28 10 3067 3 099999 3.00670+ 4 6.63522+ 1 0 0 0 03067 3103 1 2.07400+ 5 2.07400+ 5 0 0 1 173067 3103 2 17 2 3067 3103 3 1.00000- 5 0.00000+ 0 1.00000+ 6 0.00000+ 0 1.50000+ 6 3.60000- 43067 3103 4 2.00000+ 6 2.60000- 3 2.50000+ 6 8.40000- 3 3.00000+ 6 2.20000- 23067 3103 5 3.50000+ 6 3.40000- 2 4.00000+ 6 5.00000- 2 5.00000+ 6 5.10000- 23067 3103 6 6.00000+ 6 5.80000- 2 8.00000+ 6 7.40000- 2 1.00000+ 7 8.50000- 23067 3103 7 1.20000+ 7 7.90000- 2 1.40000+ 7 5.90000- 2 1.60000+ 7 4.10000- 23067 3103 8 1.80000+ 7 2.60000- 2 2.00000+ 7 1.50000- 2 3067 3103 9 3067 3 099999 3067 0 0 0 3.00670+ 4 6.63522+ 1 0 0 1 13067 8 22 1 2.80630+ 4 0.00000+ 0 3 0 0 03067 8 22 2 3067 8 099999 3.00670+ 4 6.63522+ 1 0 0 1 13067 8 28 1 2.90660+ 4 0.00000+ 0 3 0 0 03067 8 28 2 3067 8 099999 3.00670+ 4 6.63522+ 1 0 0 1 13067 8103 1 2.90670+ 4 0.00000+ 0 3 0 0 03067 8103 2 3067 8 099999 3067 0 0 0 0 0 0 0 0.000000+0 0.000000+0 0 0 0 0 -1 0 0 0