ENTRY 23795 20210220 23012379500000001 SUBENT 23795001 20210220 23012379500100001 BIB 13 28 2379500100002 TITLE Search for A = 60 fragments from neutron-induced 2379500100003 fission with accelerator mass spectrometry 2379500100004 AUTHOR (K.Knie,A.Elhardt,T.Faestermann,G.Korschinek,C.Lierse, 2379500100005 G.Rugel,A.Stippschild) 2379500100006 REFERENCE (J,NP/A,723,343,2003) 2379500100007 INSTITUTE (2GERMUN) 2379500100008 FACILITY (REAC,2GERMUN) Munich research reactor. 2379500100009 INC-SOURCE (REAC) 2379500100010 INC-SPECT Thermal neutrons. 2379500100011 Neutron fluence was calculated to be 1.7E+18 cm**-2 2379500100012 using Fe-58 cross section 1.153 b from 2379500100013 Korea Atomic Energy Research Institute. 2379500100014 ASSUMED (ASSUM,26-FE-58(N,G)26-FE-59,,SIG,,MXW) 2379500100015 SAMPLE 1.07 mg of enriched (58.4%) Fe-58 2379500100016 METHOD (ACTIV,GSPEC) Irradiation time 24 hr. 2379500100017 Decay corrected Fe-59 activity 2.30+-0.02 MBq was 2379500100018 measured with gamma spectroscopy. 2379500100019 Fe-60/Fe-58 ratio (1.0+-0.2)*10**-1 was measured by 2379500100020 AMS (accelerator mass spectrometry). 2379500100021 CORRECTION Contribution of epi-thermal and fast neutrons was 2379500100022 neglected. 2379500100023 ADD-RES . Upper limit 1.E-8 % for mass A=60 fission chain yield2379500100024 was measured by AMS method using a sample chemically 2379500100025 extracted from radioactive waste concentrate of the 2379500100026 reprocessing plant WAK in Karlsruhe, Germany. 2379500100027 . Table 1 - model calculations for the double neutron 2379500100028 capture production of Fe-60. 2379500100029 HISTORY (20210220C) M.M. 2379500100030 ENDBIB 28 0 2379500100031 COMMON 1 3 2379500100032 ASSUM 2379500100033 B 2379500100034 1.153 2379500100035 ENDCOMMON 3 0 2379500100036 ENDSUBENT 35 0 2379500199999 SUBENT 23795002 20210220 23012379500200001 BIB 4 7 2379500200002 REACTION (26-FE-59(N,G)26-FE-60,,SIG,,MXW) 2379500200003 COMMENT Of authors. This cross-section was measured to estimate2379500200004 production of Fe-60 via neutron capture reaction. 2379500200005 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2379500200006 article. 2379500200007 STATUS (TABLE) Text page 349 of 2379500200008 Nucl.Phys.Part A,v.723,p.343,2003 2379500200009 ENDBIB 7 0 2379500200010 NOCOMMON 0 0 2379500200011 DATA 3 1 2379500200012 EN-DUMMY DATA DATA-ERR 2379500200013 EV B B 2379500200014 0.0253 6.0 1.3 2379500200015 ENDDATA 3 0 2379500200016 ENDSUBENT 15 0 2379500299999 ENDENTRY 2 0 2379599999999