ENTRY 40743 20180315 41784074300000001 SUBENT 40743001 20180315 41784074300100001 BIB 7 18 4074300100002 AUTHOR (I.A.Kondurov, A.I.Egorov, M.Kaminker, E.M.Korotkikh, 4074300100003 A.M.Nikitin) 4074300100004 TITLE Neutron capture cross sections measurements for Co58m,4074300100005 Cu64, and Sc46 4074300100006 INSTITUTE (4RUSFTI) 4074300100007 REFERENCE (J,AE,24,533,1968) Is.6. Main reference. Data are given4074300100008 (J,SJA,24,657,1968) Engl.transl.of J,AE,24,533,1968 4074300100009 (P,INDC-140,22,1966) 4074300100010 Co-58m, Sc-46 capture CS - preliminary data. 4074300100011 METHOD (BURN) Burn-up 4074300100012 FACILITY (REAC,4RUSFTI) Reactor WWR-M 4074300100013 HISTORY (19840516T) Converted from ENTRY 80143 4074300100014 (19970710A) * * Corrected in CJD - S.Maev *** 4074300100015 (20180315A) M.M. Upper -> lower case correction. 4074300100016 Dates were corrected for 4-digits year. 4074300100017 Ref. SJA,24,657,1968 was added. 4074300100018 BIB information was added. 4074300100019 Subent 008 was added. 4074300100020 ENDBIB 18 0 4074300100021 NOCOMMON 0 0 4074300100022 ENDSUBENT 21 0 4074300199999 SUBENT 40743002 20180315 41784074300200001 BIB 4 7 4074300200002 REACTION (21-SC-46(N,G)21-SC-47,,SIG,,SPA) 4074300200003 INC-SPECT Reactor spectrum. cadmium ratio is 19.3 +- 0.6 4074300200004 STATUS (TABLE) P,INDC-140,22,1966 4074300200005 (PRELM) 4074300200006 (SPSDD,40743007) 4074300200007 HISTORY (19970710A) Data superseded as not corresponding 4074300200008 to those given in the main reference 4074300200009 ENDBIB 7 0 4074300200010 NOCOMMON 0 0 4074300200011 DATA 2 1 4074300200012 EN-DUMMY DATA-MAX 4074300200013 MEV B 4074300200014 2.5300E-08 2.0000E+00 4074300200015 ENDDATA 3 0 4074300200016 ENDSUBENT 15 0 4074300299999 SUBENT 40743003 20180315 41784074300300001 BIB 5 12 4074300300002 REACTION (27-CO-58-M(N,G)27-CO-59,,SIG) 4074300300003 ANALYSIS SIG0 was derived from SPA cross section - see formula 4074300300004 (2) in SJA,24,657,1968 : 4074300300005 SIG0=SIGspa/(g+r*S0*SQRT(T/T0)), where 4074300300006 r*SQRT(T/T0) = 0.025+-0.02, S0=6.3+-1.2, 4074300300007 Westcott factor g was assumed to be 1. . 4074300300008 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 4074300300009 STATUS (TABLE) Text, page 659 of SJA,24,657,1968 4074300300010 (DEP,40743008) SPA cross section 4074300300011 HISTORY (19970710U) BIB-information added 4074300300012 (20180315A) M.M. EN-DUMMY -> EN, SPA deleted ( 2200 4074300300013 m/sec SIG0) . 4074300300014 ENDBIB 12 0 4074300300015 NOCOMMON 0 0 4074300300016 DATA 3 1 4074300300017 EN DATA DATA-ERR 4074300300018 EV B B 4074300300019 0.0253 1.36E+05 1.0E+04 4074300300020 ENDDATA 3 0 4074300300021 ENDSUBENT 20 0 4074300399999 SUBENT 40743004 20180315 41784074300400001 BIB 4 5 4074300400002 REACTION (27-CO-58-M(N,G)27-CO-59,,RI) 4074300400003 ANALYSIS RI was derived from SIG0 : RI=1/2 * SQRT(PI*SIG0) 4074300400004 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 4074300400005 STATUS (TABLE) Text, page 662 of SJA,24,657,1968 4074300400006 (DEP,40743003) SIG0 4074300400007 ENDBIB 5 0 4074300400008 NOCOMMON 0 0 4074300400009 DATA 3 1 4074300400010 EN-MIN DATA DATA-ERR 4074300400011 MEV B B 4074300400012 5.0000E-07 7.60E+05 1.60E+05 4074300400013 ENDDATA 3 0 4074300400014 ENDSUBENT 13 0 4074300499999 SUBENT 40743005 20180315 41784074300500001 BIB 5 8 4074300500002 REACTION ((28-NI-58(N,P)27-CO-58-M,,SIG,,SPA)/ 4074300500003 (28-NI-58(N,P)27-CO-58,,SIG,,SPA)) 4074300500004 INC-SPECT Reactor spectrum. Cd ratio is 19.3+-0.6 for Co59 4074300500005 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 4074300500006 STATUS (SCSRS) 4074300500007 HISTORY (19970710U) BIB-info added 4074300500008 (20180315U) M.M. Data were not found in SJA,24,657,19684074300500009 INDC-140 is not available for checking 4074300500010 ENDBIB 8 0 4074300500011 NOCOMMON 0 0 4074300500012 DATA 3 1 4074300500013 EN-DUMMY DATA DATA-ERR 4074300500014 MEV NO-DIM NO-DIM 4074300500015 2.5300E-08 4.8000E-01 4.0000E-03 4074300500016 ENDDATA 3 0 4074300500017 ENDSUBENT 16 0 4074300599999 SUBENT 40743006 20180315 41784074300600001 BIB 8 11 4074300600002 REACTION (29-CU-64(N,G)29-CU-65,,SIG,,MXW) 4074300600003 DETECTOR (SCIN) Scintillation spectrometer 4074300600004 INC-SPECT Reactor spectrum. Cd ratio is 19.3 +- 0.6 for Co59 4074300600005 Thermal neutron flux 2.E+14 n/cm2/sec. 4074300600006 DECAY-DATA (29-CU-64,12.838HR,DG) 4074300600007 COMMENT Of authors. Because error is too large, then only 4074300600008 conclusion was done, that this CS < 6000 b - upper 4074300600009 limit estimated as SIG+2*ERR with 95% probability. 4074300600010 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 4074300600011 STATUS (TABLE) Text, page 660 of SJA,24,657,1968 4074300600012 HISTORY (19970710T) * * Converted from SUBENT 80501004 4074300600013 ENDBIB 11 0 4074300600014 NOCOMMON 0 0 4074300600015 DATA 3 1 4074300600016 EN-DUMMY DATA DATA-ERR 4074300600017 EV B B 4074300600018 2.5300E-02 2.100E+03 1.900E+03 4074300600019 ENDDATA 3 0 4074300600020 ENDSUBENT 19 0 4074300699999 SUBENT 40743007 20180315 41784074300700001 BIB 10 15 4074300700002 REACTION (21-SC-46(N,G)21-SC-47,,SIG,,MXW) 4074300700003 SAMPLE Scandium oxide samples. 4074300700004 INC-SPECT Reactor spectrum. Cd ratio is 19.3 +- 0.6 for Co59 4074300700005 DETECTOR Germanium semiconductor spectrometer 4074300700006 DECAY-DATA (21-SC-46-G,84.D,B-,,,DG,889.,,DG,1119.) 4074300700007 (21-SC-47,3.4D,B-,,,DG,157.) 4074300700008 Lines in measured gamma spectra of irradiated samples.4074300700009 METHOD (ACTIV,CHSEP,GSPEC) Irradiation 1-10 days. 4074300700010 Single spectrum was measured 3-5 hr. 4074300700011 ASSUMED (ASSUM,21-SC-45(N,G)21-SC-46,,SIG,,MXW) 4074300700012 ERR-ANALYS (DATA-ERR) Type of error is not explained in article 4074300700013 STATUS (TABLE) Text, page 662 of SJA,24,657,1968 4074300700014 HISTORY (19970710T) * * Converted from SUBENT 80501005 4074300700015 (20180315A) M.M. Decay data were corrected. 4074300700016 Code BA was deleted from SF5 . 4074300700017 ENDBIB 15 0 4074300700018 NOCOMMON 0 0 4074300700019 DATA 4 1 4074300700020 EN-DUMMY DATA DATA-ERR ASSUM 4074300700021 EV B B B 4074300700022 2.5300E-02 8.3 1.4 2.2000E+01 4074300700023 ENDDATA 3 0 4074300700024 ENDSUBENT 23 0 4074300799999 SUBENT 40743008 20180315 41784074300800001 BIB 11 26 4074300800002 REACTION (27-CO-58-M(N,G)27-CO-59,,SIG,,SPA) 4074300800003 SAMPLE Co-58-M was produced via Ni-58(n,p) reaction at fast 4074300800004 neutron irradiation . 4074300800005 INC-SPECT Reactor spectrum. Cd ratio is 19.3 +- 0.6 for Co-59 4074300800006 METHOD Ni samples of 0.1-1.0 g were irradiated in the water 4074300800007 cavity of reactor at fast and thermal neutron flux of 4074300800008 (2-3)*10**13 and 2*10**14 n/cn2/sec, respectively. 4074300800009 Irradiation time 10-30 hr. 4074300800010 Irradiation without (2samples) and with (1 sample) Cd.4074300800011 (CHSEP) Chemical separation (1hr) of Co from Ni was 4074300800012 employed. 4074300800013 MONITOR Thermal neutron flux was determined by Co monitors 4074300800014 with accuracy 3-4 %. 4074300800015 DETECTOR (SCIN) Co-58 activity was measured by scintillation 4074300800016 spectrometer during 2-3 days. 4074300800017 ASSUMED (ASSUM,27-CO-59(N,G)27-CO-60,,SIG) For 2200 m/sec 4074300800018 Co-58 capture CS at thermal point was defined as 4074300800019 weighted average of two values 1650+-150 and 4074300800020 3150+-150 b 4074300800021 DECAY-DATA CO-58-M mean lifetime 13.3+-0.2 hr measured , 4074300800022 Isomeric transition 25 keV . 4074300800023 (27-CO-58-G,71.3D,DG,814.) 4074300800024 ERR-ANALYS (ERR-1,3.,4.) Neutron flux uncertainty . 4074300800025 (DATA-ERR) Type of error is not explained in article 4074300800026 STATUS (TABLE) Text, page 659 of SJA,24,657,1968 4074300800027 HISTORY (20180315C) M.M. 4074300800028 ENDBIB 26 0 4074300800029 NOCOMMON 0 0 4074300800030 DATA 5 1 4074300800031 EN-DUMMY DATA DATA-ERR ASSUM ASSUM-ERR 4074300800032 EV B B B B 4074300800033 0.0253 1.57E+05 1.0E+04 37.5 1.0 4074300800034 ENDDATA 3 0 4074300800035 ENDSUBENT 34 0 4074300899999 ENDENTRY 8 0 4074399999999