ENTRY 31631 20160929 31753163100000001 SUBENT 31631001 20160929 31753163100100001 BIB 13 34 3163100100002 TITLE Measurement of thermal neutron cross sections of the 3163100100003 reactions 126Sn(n,gamma)127g,127mSn 3163100100004 AUTHOR (Sheng-Dong Zhang,Lei Yang,Jingru Guo,Fangding Wang, 3163100100005 An-Zhi Cui,Lijun Diao) 3163100100006 INSTITUTE (3CPRAEP) 3163100100007 REFERENCE (J,RCA,94,385,2006) 3163100100008 FACILITY (REAC,3CPRAEP) 3163100100009 SAMPLE About 4-10 Bq of 126Sn carried by PbS precipitate 3163100100010 was used as target, because PbS does not produce any 3163100100011 gamma-emitting nuclide on irradiation, and can 3163100100012 co-precipitate 126Sn completely. The PbS (126Sn) was 3163100100013 deposited on the bottom of the polyethylene box as a 3163100100014 thin layer. The polyethylene box was sealed and 3163100100015 housed in an Al can together with the neutron flux 3163100100016 monitors 197Au and 55Mn. 3163100100017 The number of the 126Sn atoms in the samples were 3163100100018 determined by the activities of the 126Sn beta-decay 3163100100019 product Sb-126m and Sb-126g. The sample was aged for 753163100100020 days to reach secular equilibrium. 3163100100021 INC-SOURCE The thermal neutron fluxes of three irradiation runs 3163100100022 were found to be 2.09x10**13 n/cm2/s, 1.77x10**13 3163100100023 n/cm2/s and 2.02x10**13 n/cm2/s, respectively, by 3163100100024 using the neutron activation equation. 3163100100025 DETECTOR (HPGE) 3163100100026 METHOD (ACTIV,GSPEC,CHSEP) 3163100100027 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) - Neutron flux monitor 3163100100028 (25-MN-55(N,G)25-MN-56,,SIG) - Neutron flux monitor 3163100100029 DECAY-MON (79-AU-198-G,2.69D,DG,411.8,0.947) 3163100100030 (25-MN-56,2.578HR,DG,846.7,0.989) 3163100100031 STATUS (TABLE) from the abstract. 3163100100032 HISTORY (20080724C) SD 3163100100033 (20160923A) VS. SF8=SPA deleted in 002-004; 3163100100034 EN-DUMMY->EN; DECAY-DATA corrected in 002 and 004; 3163100100035 ERR-ANALYS modified 002-003. 3163100100036 ENDBIB 34 0 3163100100037 COMMON 1 3 3163100100038 EN 3163100100039 EV 3163100100040 0.0253 3163100100041 ENDCOMMON 3 0 3163100100042 ENDSUBENT 41 0 3163100199999 SUBENT 31631002 20160929 31753163100200001 BIB 6 13 3163100200002 REACTION (50-SN-126(N,G)50-SN-127-M,,SIG) 3163100200003 DECAY-DATA (50-SN-127-M,4.13MIN) 3163100200004 (51-SB-127,3.85D,DG,473.2,0.248,DG,684.9,0.368, 3163100200005 DG,782.6,0.15) 3163100200006 (50-SN-127-G,2.10HR) 3163100200007 RAD-DET (51-SB-127,DG) 3163100200008 ERR-ANALYS (ERR-T) The largest uncertainty comes from the average 3163100200009 deviation in two irradiated targets. 3163100200010 (ERR-1,2.6,2.8) error in 127Sb radioactivity 3163100200011 (ERR-2,2.0,4.7) error of the thermal neutron flux 3163100200012 STATUS (DEP,31631003) 3163100200013 HISTORY (20160923A) VS. SF8=SPA deleted; DECAY-DATA corrected; 3163100200014 ERR-ANALYS modified. 3163100200015 ENDBIB 13 0 3163100200016 NOCOMMON 0 0 3163100200017 DATA 2 1 3163100200018 DATA ERR-T 3163100200019 B B 3163100200020 0.39 0.1 3163100200021 ENDDATA 3 0 3163100200022 ENDSUBENT 21 0 3163100299999 SUBENT 31631003 20160929 31753163100300001 BIB 4 10 3163100300002 REACTION (50-SN-126(N,G)50-SN-127-G,,SIG) 3163100300003 DECAY-DATA (50-SN-127-G,2.10HR,DG,823.1,0.1064,DG,1095.6,0.1938, 3163100300004 DG,1114.3,0.38) 3163100300005 ERR-ANALYS (ERR-T) The uncertainty consists of the average 3163100300006 deviation of cross sections from three irradiated 3163100300007 targets. 3163100300008 (ERR-S,5.6,8.5) 127gSn counting statistics, error of 3163100300009 the weighted average and error of counting efficiency 3163100300010 (ERR-1,2.0,4.7) error of the thermal neutron flux 3163100300011 HISTORY (20160923A) VS. SF8=SPA deleted. ERR-ANALYS modified. 3163100300012 ENDBIB 10 0 3163100300013 NOCOMMON 0 0 3163100300014 DATA 2 1 3163100300015 DATA ERR-T 3163100300016 B B 3163100300017 0.200 0.039 3163100300018 ENDDATA 3 0 3163100300019 ENDSUBENT 18 0 3163100399999 SUBENT 31631004 20160929 31753163100400001 BIB 4 5 3163100400002 REACTION (50-SN-126(N,G)50-SN-127,,SIG) 3163100400003 ERR-ANALYS (ERR-T) see above (subents 002,003) 3163100400004 STATUS (DEP,31631002) 3163100400005 (DEP,31631003) 3163100400006 HISTORY (20160923A) VS. SF8=SPA deleted, DECAY-DATA deleted. 3163100400007 ENDBIB 5 0 3163100400008 NOCOMMON 0 0 3163100400009 DATA 2 1 3163100400010 DATA ERR-T 3163100400011 B B 3163100400012 0.59 0.14 3163100400013 ENDDATA 3 0 3163100400014 ENDSUBENT 13 0 3163100499999 ENDENTRY 4 0 3163199999999