ENTRY 22632 20090818 22172263200000001 SUBENT 22632001 20090818 22172263200100001 BIB 15 33 2263200100002 TITLE .Measurements of Thermal Neutron Capture Cross Sections2263200100003 For Some Fission Product Nuclides 2263200100004 AUTHOR (S.Nakamura, K.Furutaka, H.Harada, T.Katoh) 2263200100005 INSTITUTE (2JPNPNC) Nakamura, Furutaka, Harada. 2263200100006 Comment: Institute code corresponds to the time 2263200100007 of publication 2263200100008 (2JPNGMT) Katoh, GIFU College of Med. Technology 2263200100009 REFERENCE (S,JAERI-C-99-002,176,199903) Main Reference 2263200100010 REL-REF (M,22295001,H.Harada+,J,NST,32,(5),395,199505) 2263200100011 Experimental details. 2263200100012 FACILITY (REAC,2JPNYOK) 2263200100013 INC-SOURCE (REAC) Rotary Specimen Rack of the Research Reactor 2263200100014 TRIGA MK-II 2263200100015 METHOD (ACTIV) Activation 2263200100016 (GSPEC) Gamma-ray spectroscopy 2263200100017 DETECTOR (HPGE) Energy resolution 2.1 keV at 1.33 MeV of Co-60 2263200100018 90 % relative efficiency. 2263200100019 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 2263200100020 (27-CO-59(N,G)27-CO-60,,SIG) 2263200100021 SAMPLE -0.112Wt% Au/Al alloy, 0.510 mm diameter, and 2263200100022 0.46Wt% Co/Al Alloy 0.381 mm diameter - monitor 2263200100023 samples. 2263200100024 INC-SPECT -Each sample was irradiated without and with 2263200100025 cadmium capsule to reduce the thermal neutron flux 2263200100026 at the target. 2263200100027 ERR-ANALYS (DATA-ERR) Errors not specified. 2263200100028 Supposed total by compiler . 2263200100029 STATUS (COREL,22834001) 2263200100030 HISTORY (20010804C) + + Compiled by S.M. 2263200100031 (20051109A) .Correlation to data in ENTRY 22834 2263200100032 (20090818A) M.M. COREL replaced by SPSDD in STATUS of 2263200100033 22632.002-009. ERR-T -> DATA-ERR . 2263200100034 Ref. J,NST,32,(5),395,1995 was moved in REL-REF. 2263200100035 ENDBIB 33 0 2263200100036 NOCOMMON 0 0 2263200100037 ENDSUBENT 36 0 2263200199999 SUBENT 22632002 20090818 22172263200200001 BIB 4 5 2263200200002 REACTION (34-SE-80(N,G)34-SE-81-M,,SIG,,MXW) 2263200200003 SAMPLE No information. 2263200200004 INC-SPECT .Maxwell neutron energy distribution 2263200200005 STATUS (TABLE) From Table 2 of S,JAERI-C-99-002,176,1999 . 2263200200006 (SPSDD,22834002) 2263200200007 ENDBIB 5 0 2263200200008 NOCOMMON 0 0 2263200200009 DATA 3 1 2263200200010 EN-MEAN DATA DATA-ERR 2263200200011 EV B B 2263200200012 2.53E-02 0.046 0.002 2263200200013 ENDDATA 3 0 2263200200014 ENDSUBENT 13 0 2263200299999 SUBENT 22632003 20090818 22172263200300001 BIB 5 6 2263200300002 REACTION (34-SE-80(N,G)34-SE-81-G,,SIG,,MXW) 2263200300003 SAMPLE No information . 2263200300004 INC-SPECT .Maxwell neutron energy distribution 2263200300005 STATUS (TABLE) From Table 2 of S,JAERI-C-99-002,176,1999 . 2263200300006 (SPSDD,22834004) 2263200300007 HISTORY (20051109A) Metastable code 'M' changed to 'G' 2263200300008 ENDBIB 6 0 2263200300009 NOCOMMON 0 0 2263200300010 DATA 3 1 2263200300011 EN-MEAN DATA DATA-ERR 2263200300012 EV B B 2263200300013 2.53E-02 0.542 0.042 2263200300014 ENDDATA 3 0 2263200300015 ENDSUBENT 14 0 2263200399999 SUBENT 22632004 20090818 22172263200400001 BIB 4 5 2263200400002 REACTION (34-SE-80(N,G)34-SE-81-M,,RI) 2263200400003 SAMPLE No information. 2263200400004 STATUS (TABLE) From Table 2 of S,JAERI-C-99-002,176,1999 . 2263200400005 (SPSDD,22834003) 2263200400006 HISTORY (20051109A) '81-G' corrected into '81-M' . 2263200400007 ENDBIB 5 0 2263200400008 NOCOMMON 0 0 2263200400009 DATA 3 1 2263200400010 EN-MIN DATA DATA-ERR 2263200400011 EV B B 2263200400012 0.45 0.147 0.005 2263200400013 ENDDATA 3 0 2263200400014 ENDSUBENT 13 0 2263200499999 SUBENT 22632005 20090818 22172263200500001 BIB 4 5 2263200500002 REACTION (34-SE-80(N,G)34-SE-81-G,,RI) 2263200500003 DECAY-DATA (34-SE-81-G,18.45MIN) Taken from Nuclear Wallet Card 2263200500004 SAMPLE No information. 2263200500005 STATUS (TABLE) From Table 2 of S,JAERI-C-99-002,176,1999. 2263200500006 (SPSDD,22834005) 2263200500007 ENDBIB 5 0 2263200500008 NOCOMMON 0 0 2263200500009 DATA 3 1 2263200500010 EN-MIN DATA DATA-ERR 2263200500011 EV B B 2263200500012 0.45 0.847 0.071 2263200500013 ENDDATA 3 0 2263200500014 ENDSUBENT 13 0 2263200599999 SUBENT 22632006 20090818 22172263200600001 BIB 5 6 2263200600002 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG,,MXW) 2263200600003 DECAY-DATA (40-ZR-95,64.02D) Taken from Nuclear Wallet Card 2263200600004 INC-SPECT .Maxwell neutron energy distribution. 2263200600005 SAMPLE No information. 2263200600006 STATUS (TABLE) From Table 3 of S,JAERI-C-99-002,176,1999. 2263200600007 (SPSDD,22834006) 2263200600008 ENDBIB 6 0 2263200600009 NOCOMMON 0 0 2263200600010 DATA 3 1 2263200600011 EN-MEAN DATA DATA-ERR 2263200600012 EV B B 2263200600013 2.53E-02 0.0479 0.001 2263200600014 ENDDATA 3 0 2263200600015 ENDSUBENT 14 0 2263200699999 SUBENT 22632007 20090818 22172263200700001 BIB 3 4 2263200700002 REACTION (40-ZR-94(N,G)40-ZR-95,,RI) 2263200700003 SAMPLE No information . 2263200700004 STATUS (TABLE) From Table 3 of S,JAERI-C-99-002,176,1999. 2263200700005 (SPSDD,22834007) 2263200700006 ENDBIB 4 0 2263200700007 NOCOMMON 0 0 2263200700008 DATA 3 1 2263200700009 EN-MIN DATA DATA-ERR 2263200700010 EV B B 2263200700011 0.45 0.277 0.007 2263200700012 ENDDATA 3 0 2263200700013 ENDSUBENT 12 0 2263200799999 SUBENT 22632008 20090818 22172263200800001 BIB 4 5 2263200800002 REACTION (50-SN-124(N,G)50-SN-125-G,,SIG,,MXW) 2263200800003 SAMPLE No information . 2263200800004 INC-SPECT .Maxwell neutron energy distribution . 2263200800005 STATUS (TABLE) From Table 4 of S,JAERI-C-99-002,176,1999. 2263200800006 (SPSDD,22834012) 2263200800007 ENDBIB 5 0 2263200800008 NOCOMMON 0 0 2263200800009 DATA 3 1 2263200800010 EN-MEAN DATA DATA-ERR 2263200800011 EV B B 2263200800012 2.54E-02 0.0042 0.0013 2263200800013 ENDDATA 3 0 2263200800014 ENDSUBENT 13 0 2263200899999 SUBENT 22632009 20090818 22172263200900001 BIB 3 4 2263200900002 REACTION (50-SN-124(N,G)50-SN-125-G,,RI) 2263200900003 SAMPLE No information . 2263200900004 STATUS (TABLE) From Table 4 of S,JAERI-C-99-002,176,1999 . 2263200900005 (SPSDD,22834013) 2263200900006 ENDBIB 4 0 2263200900007 NOCOMMON 0 0 2263200900008 DATA 3 1 2263200900009 EN-MIN DATA DATA-ERR 2263200900010 EV B B 2263200900011 0.45 0.083 0.025 2263200900012 ENDDATA 3 0 2263200900013 ENDSUBENT 12 0 2263200999999 ENDENTRY 9 0 2263299999999