ENTRY 13129 20120711 13841312900000001 SUBENT 13129001 20120711 13841312900100001 BIB 14 24 1312900100002 INSTITUTE (1USAIRV) 1312900100003 REFERENCE (J,JRN,113,327,198707) 1312900100004 AUTHOR (M.Gavrilas,V.P.Guinn) 1312900100005 TITLE Environmental importance of the 107Ag(n,gamma)108mAg 1312900100006 reaction in nuclear power reactors, and new sigma- 1312900100007 zero(gamma) and I(gamma) measurements 1312900100008 FACILITY (REAC,1USAIRV) U.C.Irving 250 KW TRIGA reactor 1312900100009 DETECTOR (GELI) 17% coaxial Ge(Li) detector with a 1312900100010 2.0 cm thick plastic beta-particle absorber 1312900100011 SAMPLE (47-AG-107,ENR=0.9822) Samples enriched to 98.22% 107Ag1312900100012 57.1 mg sample without Cd, 46.2 mg sample sealed 1312900100013 in Cd 0.70 mm thick. 1312900100014 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) Flux monitor 1312900100015 DECAY-DATA (47-AG-108-M,127.YR,DG,433.9,,DG,614.4,,DG,723.0) 1312900100016 DECAY-MON (47-AG-110-M,249.76D,DG,657.7) 1312900100017 ERR-ANALYS Detailed information not available. Uncertainties do 1312900100018 not include uncertainties in normalizing values of 1312900100019 110-Ag. 1312900100020 CORRECTION Gamma-gamma coincidence loss correction 1312900100021 STATUS (TABLE) Data from the text of JRN,113,327,1987 1312900100022 No reply to author proof 1312900100023 HISTORY (19880405C) 1312900100024 (20120711A) SD:Updated to new date formats,lower case. 1312900100025 Corrected according to last EXFOR rules and Dict. 1312900100026 ENDBIB 24 0 1312900100027 NOCOMMON 0 0 1312900100028 ENDSUBENT 27 0 1312900199999 SUBENT 13129002 20120711 13841312900200001 BIB 3 3 1312900200002 REACTION (47-AG-107(N,G)47-AG-108-M,,SIG) 1312900200003 INC-SOURCE The resulting neutron flux was 9.0 x 10**11 n/cm2/s 1312900200004 MONITOR ((MONIT)47-AG-109(N,G)47-AG-110-M,,SIG) 1312900200005 ENDBIB 3 0 1312900200006 NOCOMMON 0 0 1312900200007 DATA 5 1 1312900200008 EN DATA DATA-ERR MONIT MONIT-ERR 1312900200009 EV B B B B 1312900200010 0.0253 0.477 0.033 4.7 0.2 1312900200011 ENDDATA 3 0 1312900200012 ENDSUBENT 11 0 1312900299999 SUBENT 13129003 20120711 13841312900300001 BIB 3 3 1312900300002 REACTION (47-AG-107(N,G)47-AG-108-M,,RI) 1312900300003 MONITOR ((MONIT)47-AG-109(N,G)47-AG-110-M,,RI) 1312900300004 INC-SOURCE The resulting neutron flux was 2.0 x 10**10 n/cm2/s 1312900300005 ENDBIB 3 0 1312900300006 NOCOMMON 0 0 1312900300007 DATA 5 1 1312900300008 EN-MIN DATA DATA-ERR MONIT MONIT-ERR 1312900300009 EV B B B B 1312900300010 0.5 0.80 0.15 72.3 4.0 1312900300011 ENDDATA 3 0 1312900300012 ENDSUBENT 11 0 1312900399999 ENDENTRY 3 0 1312999999999