ENTRY 23401 20201210 22962340100000001 SUBENT 23401001 20201210 22962340100100001 BIB 13 21 2340100100002 TITLE Measurements of the averaged neutron cross section of 2340100100003 some threshold reactions for fission neutrons 2340100100004 AUTHOR (K.Kanda, H.Chatani, T.Shibata) 2340100100005 INSTITUTE (2JPNKTO) 2340100100006 REFERENCE (R,KURRI-AR-4,94,1971) Preliminary note 2340100100007 FACILITY (REAC,2JPNKTO) KUR Heavy Water Facility 2340100100008 INC-SOURCE UO2-Al cermet (90% enriched uranium, 27 cm diam., 2340100100009 equivalent thickness of uranium of 1.95 g/cm2) 2340100100010 in thermal neutron field (7E+9 neutrons/cm2/sec) 2340100100011 INC-SPECT 235U prompt fission neutron spectrum 2340100100012 METHOD (ACTIV) Irradiated for ~40 hrs 2340100100013 MONITOR (13-AL-27(N,A)11-NA-24,,SIG,,FIS) 2340100100014 DECAY-MON (11-NA-24,15.HR,DG,1375.,1.) 2340100100015 ERR-ANALYS (ERR-T) Total uncertainty due to 2340100100016 counting statistics, 2340100100017 photopeak efficiency, as well as 2340100100018 (ERR-1) geometrical error (0.5%) 2340100100019 (ERR-2) foil weight (0.4%) 2340100100020 STATUS (TABLE) Abstract of Ann.Rep.RRI Kyoto Univ.4(1971)94 2340100100021 HISTORY (20190122C) On 2340100100022 (20201210A) SD: Correction in Subent 005. 2340100100023 ENDBIB 21 0 2340100100024 COMMON 3 3 2340100100025 MONIT ERR-1 ERR-2 2340100100026 MB PER-CENT PER-CENT 2340100100027 0.61 0.5 0.4 2340100100028 ENDCOMMON 3 0 2340100100029 ENDSUBENT 28 0 2340100199999 SUBENT 23401002 20180909 22752340100200001 BIB 3 3 2340100200002 REACTION (12-MG-24(N,P)11-NA-24,,SIG,,FIS) 2340100200003 DECAY-DATA (11-NA-24,15.HR,DG,1375.,1.) 2340100200004 DETECTOR (NAICR,GELI) 2340100200005 ENDBIB 3 0 2340100200006 NOCOMMON 0 0 2340100200007 DATA 3 1 2340100200008 KT-DUMMY DATA ERR-T 2340100200009 MEV MB MB 2340100200010 1.32 1.28 0.04 2340100200011 ENDDATA 3 0 2340100200012 ENDSUBENT 11 0 2340100299999 SUBENT 23401003 20180909 22752340100300001 BIB 3 3 2340100300002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 2340100300003 DECAY-DATA (27-CO-58-G,71.3D,DG,810.,0.99) 2340100300004 DETECTOR (NAICR,GELI) 2340100300005 ENDBIB 3 0 2340100300006 NOCOMMON 0 0 2340100300007 DATA 3 1 2340100300008 KT-DUMMY DATA ERR-T 2340100300009 MEV MB MB 2340100300010 1.32 112. 3. 2340100300011 ENDDATA 3 0 2340100300012 ENDSUBENT 11 0 2340100399999 SUBENT 23401004 20180909 22752340100400001 BIB 3 3 2340100400002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG,,FIS) 2340100400003 DECAY-DATA (49-IN-115-M,4.5HR,DG,335.,0.5) 2340100400004 DETECTOR (NAICR,GELI) 2340100400005 ENDBIB 3 0 2340100400006 NOCOMMON 0 0 2340100400007 DATA 3 1 2340100400008 KT-DUMMY DATA ERR-T 2340100400009 MEV MB MB 2340100400010 1.32 171. 5. 2340100400011 ENDDATA 3 0 2340100400012 ENDSUBENT 11 0 2340100499999 SUBENT 23401005 20201210 22962340100500001 BIB 4 5 2340100500002 REACTION (45-RH-103(N,INL)45-RH-103-M,,SIG,,FIS) 2340100500003 DECAY-DATA (45-RH-103-M,57.MIN,XR,20.,0.004) 2340100500004 DETECTOR (NAICR) 2340100500005 HISTORY (20201210A) SD: DECAY-DATA corrected (the energy of 2340100500006 radiation was multiplied by 1000). 2340100500007 ENDBIB 5 0 2340100500008 NOCOMMON 0 0 2340100500009 DATA 3 1 2340100500010 KT-DUMMY DATA ERR-T 2340100500011 MEV MB MB 2340100500012 1.32 566. 23. 2340100500013 ENDDATA 3 0 2340100500014 ENDSUBENT 13 0 2340100599999 SUBENT 23401006 20180909 22752340100600001 BIB 3 3 2340100600002 REACTION (82-PB-204(N,INL)82-PB-204-M,,SIG,,FIS) 2340100600003 DECAY-DATA (82-PB-204-M,66.9MIN,DG,900.,1.89) 2340100600004 DETECTOR (NAICR) 2340100600005 ENDBIB 3 0 2340100600006 NOCOMMON 0 0 2340100600007 DATA 3 1 2340100600008 KT-DUMMY DATA ERR-T 2340100600009 MEV MB MB 2340100600010 1.32 8.80 0.44 2340100600011 ENDDATA 3 0 2340100600012 ENDSUBENT 11 0 2340100699999 SUBENT 23401007 20180909 22752340100700001 BIB 3 3 2340100700002 REACTION (82-PB-204(N,2N)82-PB-203,,SIG,,FIS) 2340100700003 DECAY-DATA (82-PB-203-G,52.1HR,DG,297.,0.81) 2340100700004 DETECTOR (NAICR) 2340100700005 ENDBIB 3 0 2340100700006 NOCOMMON 0 0 2340100700007 DATA 3 1 2340100700008 KT-DUMMY DATA ERR-T 2340100700009 MEV MB MB 2340100700010 1.32 1.16 0.16 2340100700011 ENDDATA 3 0 2340100700012 ENDSUBENT 11 0 2340100799999 ENDENTRY 7 0 2340199999999