ENTRY 30262 20081203 31323026200000001 SUBENT 30262001 20081203 31323026200100001 BIB 13 31 3026200100002 INSTITUTE (3POLIPJ) 3026200100003 REFERENCE (P,INR-1464,9,1973) Brief,tables. 3026200100004 AUTHOR (W.Augustyniak,A.Marcinkowsky) 3026200100005 TITLE Cross sections for fast neutron induced reactions in 3026200100006 Ag-107 and Ag-109 isotopes 3026200100007 INC-SOURCE (D-T) T(d,n)alpha reaction with 0.5 MeV deuterons 3026200100008 SAMPLE Enriched samples= 3026200100009 .Ag-107 (99.1 %) 3026200100010 .Ag-109 (99.3 %) 3026200100011 METHOD (ACTIV) Activation method. The reaction final products 3026200100012 are identified by their characteristic gamma-ray 3026200100013 transitions and half-lives obtained from the least 3026200100014 square analysis of the decay curve. 3026200100015 DETECTOR (GELI) 30 cm3 Ge(Li) detector, the relative efficiency 3026200100016 of which was measured in the energy range from 50 keV 3026200100017 to 2 MeV using the known intensity ratios of gamma-rays3026200100018 from Ra-226 and Yb-163 sources. 3026200100019 MONITOR (26-FE-56(N,P)25-MN-56,,SIG) 3026200100020 Standards taken from Santry,Butler,Can.J 3026200100021 (30-ZN-64(N,2N)30-ZN-63,,SIG) 3026200100022 Phys.42(1964)1030 and from BNL 325, 3026200100023 supplement 2,p.30-64-2. 3026200100024 PART-DET (DG) Decay gammas 3026200100025 STATUS (SPSDD) Preliminary results without correction for 3026200100026 selfabsorption of 90 keV gamma ray in the sample 3026200100027 HISTORY (19731112C) CA. 3026200100028 (20080423A) BIB section updated 3026200100029 ERR-ANALYS (DATA-ERR) include 3026200100030 .Statistical errors 3026200100031 .Uncertainty in the detector efficiency 3026200100032 .Uncertainty in the flux determination 3026200100033 ENDBIB 31 0 3026200100034 NOCOMMON 0 0 3026200100035 ENDSUBENT 34 0 3026200199999 SUBENT 30262002 20081203 31323026200200001 BIB 1 1 3026200200002 REACTION (47-AG-107(N,INL)47-AG-107-M,,SIG) 3026200200003 ENDBIB 1 0 3026200200004 COMMON 1 3 3026200200005 HL1 3026200200006 SEC 3026200200007 4.4300E+01 3026200200008 ENDCOMMON 3 0 3026200200009 NODATA 0 0 3026200200010 ENDSUBENT 9 0 3026200299999 SUBENT 30262003 20081203 31323026200300001 BIB 1 1 3026200300002 REACTION (47-AG-107(N,2N)47-AG-106-G,,SIG) 3026200300003 ENDBIB 1 0 3026200300004 COMMON 1 3 3026200300005 HL1 3026200300006 MIN 3026200300007 2.4000E+01 3026200300008 ENDCOMMON 3 0 3026200300009 NODATA 0 0 3026200300010 ENDSUBENT 9 0 3026200399999 SUBENT 30262004 20081203 31323026200400001 BIB 1 1 3026200400002 REACTION (47-AG-109(N,INL)47-AG-109-M,,SIG) 3026200400003 ENDBIB 1 0 3026200400004 COMMON 1 3 3026200400005 HL1 3026200400006 SEC 3026200400007 4.0000E+01 3026200400008 ENDCOMMON 3 0 3026200400009 NODATA 0 0 3026200400010 ENDSUBENT 9 0 3026200499999 SUBENT 30262005 20081203 31323026200500001 BIB 1 1 3026200500002 REACTION (47-AG-109(N,2N)47-AG-108-G,,SIG) 3026200500003 ENDBIB 1 0 3026200500004 COMMON 1 3 3026200500005 HL1 3026200500006 MIN 3026200500007 2.4200E+00 3026200500008 ENDCOMMON 3 0 3026200500009 NODATA 0 0 3026200500010 ENDSUBENT 9 0 3026200599999 SUBENT 30262006 20081203 31323026200600001 BIB 1 1 3026200600002 REACTION (47-AG-109(N,P)46-PD-109-M,,SIG) 3026200600003 ENDBIB 1 0 3026200600004 COMMON 1 3 3026200600005 HL1 3026200600006 MIN 3026200600007 4.7000E+00 3026200600008 ENDCOMMON 3 0 3026200600009 NODATA 0 0 3026200600010 ENDSUBENT 9 0 3026200699999 ENDENTRY 6 0 3026299999999