ENTRY 40002 20220119 42044000200000001 SUBENT 40002001 20220119 42044000200100001 BIB 15 58 4000200100002 TITLE Fast neutron radiative capture in Cu63 4000200100003 AUTHOR (V.A.Tolstikov,V.P.Koroleva,V.E.Kolesov,A.G.Dovbenko) 4000200100004 REFERENCE (J,AE,21,45,1966) Issue 1. Graph only (21 points) 4000200100005 (J,SJA,21,665,1966) English translation of At.Energija 4000200100006 (J,EAF,21,(1),45,1966) French translation of Atomnaja 4000200100007 Energija 4000200100008 ((R,YFI-6,11,1968)= 4000200100009 (R,INDC(CCP)-3/R,6,1968)) 4000200100010 Preliminary data (5 points). 4000200100011 First author A.G.Dovbenko. 4000200100012 ((R,INDC(CCP)-3,11,1969)=(R,INDC-0260E,11,1969)) 4000200100013 Engl.translation of YFI-6,11,1968. 4000200100014 INSTITUTE (4RUSFEI) 4000200100015 REL-REF (O,40001001,A.G.Dovbenko+,R,INDC(CCP)-3,11,1969) 4000200100016 Final data of cross-sections, 4000200100017 in INDC(CCP)-3,11,1969 - preliminary data. 4000200100018 FACILITY (VDG) 2.5 MeV and 5.0 MeV Van de Graaff 4000200100019 INC-SOURCE (P-LI7) Proton-lithium-7 in neutrons energy range 4000200100020 from 0.009 MeV up to 0.3 MeV 4000200100021 (P-T) Proton-tritium in energy range of neutrons 4000200100022 from 0.3 MeV to 3.5 MeV 4000200100023 SAMPLE Metallic sample 0.230 g/cm**2 thick. 4000200100024 METHOD (ACTIV) 4000200100025 DETECTOR (PROPC)Two end-type beta counters in geometry near 4PI 4000200100026 (FISCH) Fission chamber for registration of U-235 4000200100027 fission events 4000200100028 (LONGC) Long counter for background measurement, 4000200100029 neutron flux monitoring and etc. 4000200100030 MONITOR (92-U-235(N,F),,SIG) 4000200100031 For absolute normalization of cross 4000200100032 section in energy range from 0.3 MeV up to 3.5 MeV 4000200100033 see W.Davey,Nucl.Sci.And Eng.26,149,1966. 4000200100034 For absolute normalization of cross section below 4000200100035 0.3 MeV The data of this work above 0.3 MeV were used. 4000200100036 PART-DET (B-,B+) 4000200100037 CORRECTION Corrections were introduced 4000200100038 on background of neutrons scattered from material, 4000200100039 of target underlayer and target holder, 4000200100040 on background of neutrons scattered in measuring room, 4000200100041 on background of neutrons from foreign reactions, 4000200100042 on neutrons flux attenuation with distance from target,4000200100043 on 92-U-238 fission 4000200100044 on deviation of U-235 fission cross section energy 4000200100045 dependence from 1/v low in thermal neutrons energy 4000200100046 range 4000200100047 ERR-ANALYS (EN-ERR) Energy errors are explained by 4000200100048 scatter of proton energy, 4000200100049 final thickness of target, 4000200100050 angular dimensions of irradiated sample and chamber 4000200100051 (ERR-1) Includes error in energy dependence of 4000200100052 measured cross section,namely statistical errors, 4000200100053 errors in corrections,errors in U-235 fission cross 4000200100054 sections 4000200100055 (ERR-T) Includes all errors of experiment,errors 4000200100056 of supporting cross sections 4000200100057 HISTORY (19700707C) Data compiled at the centre 4000200100058 (20210622U) M.M. Update for current rules. 4000200100059 (20220119U) INDC(CCP) refs. were added. 4000200100060 ENDBIB 58 0 4000200100061 NOCOMMON 0 0 4000200100062 ENDSUBENT 61 0 4000200199999 SUBENT 40002002 20210622 41964000200200001 BIB 4 6 4000200200002 REACTION (29-CU-63(N,G)29-CU-64,,SIG) 4000200200003 DECAY-DATA (29-CU-64,12.9HR) Measured half-life of beta decay 4000200200004 STATUS (TABLE) From authors. 4000200200005 HISTORY (20210622A) Half-life of Cu-64 12.701(2) hr - 4000200200006 J.K.Tuli, Nuclear Valet Cards,2011. 4000200200007 So, correction was done in DECAY-DATA : YR -> HR. 4000200200008 ENDBIB 6 0 4000200200009 NOCOMMON 0 0 4000200200010 DATA 6 27 4000200200011 EN +EN-ERR -EN-ERR DATA ERR-1 ERR-T 4000200200012 KEV KEV KEV MB PER-CENT PER-CENT 4000200200013 9.0000E+00 5.0000E+00 5.0000E+00 1.3800E+02 7.4000E+00 9.3000E+004000200200014 2.0000E+01 6.0000E+00 6.0000E+00 8.5000E+01 5.9000E+00 8.1000E+004000200200015 5.1000E+01 9.0000E+00 9.0000E+00 4.4200E+01 9.1000E+00 1.0800E+014000200200016 1.0300E+02 1.3000E+01 1.3000E+01 2.9000E+01 4000200200017 1.7100E+02 5.0000E+01 5.6000E+01 2.9900E+01 4000200200018 2.6600E+02 5.2000E+01 5.8000E+01 2.5000E+01 6.9000E+00 8.9000E+004000200200019 3.0300E+02 3.7000E+01 3.7000E+01 2.1300E+01 5.1000E+00 7.6000E+004000200200020 3.7700E+02 5.3000E+01 6.5000E+01 1.8100E+01 8.2000E+00 1.0000E+014000200200021 4.1800E+02 3.5000E+01 3.5000E+01 1.9900E+01 5.1000E+00 7.6000E+004000200200022 4.5600E+02 5.5000E+01 6.8000E+01 1.8400E+01 8.2000E+00 1.0000E+014000200200023 5.3000E+02 3.5000E+01 3.5000E+01 1.5600E+01 5.5000E+00 7.9000E+004000200200024 6.3500E+02 3.4000E+01 3.4000E+01 1.5500E+01 5.3000E+00 7.7000E+004000200200025 6.9300E+02 7.0000E+01 8.0000E+01 1.5400E+01 5.4000E+00 7.8000E+004000200200026 7.0800E+02 7.0000E+01 8.0000E+01 1.5400E+01 6.4000E+00 8.6000E+004000200200027 7.4000E+02 3.4000E+01 3.4000E+01 1.4200E+01 5.1000E+00 7.6000E+004000200200028 8.9000E+02 7.4000E+01 9.3000E+01 1.5800E+01 7.5000E+00 9.4000E+004000200200029 9.5000E+02 3.3000E+01 3.3000E+01 1.3900E+01 5.1000E+00 7.6000E+004000200200030 1.0600E+03 7.8000E+01 1.0000E+02 1.4300E+01 1.0300E+01 1.1500E+014000200200031 1.1540E+03 3.3000E+01 3.3000E+01 1.3100E+01 1.1200E+01 1.2400E+014000200200032 1.3560E+03 3.2000E+01 3.2000E+01 1.0600E+01 6.3000E+00 6.5000E+004000200200033 1.4600E+03 3.4000E+01 3.4000E+01 1.0800E+01 7.1000E+00 9.1000E+004000200200034 1.5040E+03 7.0000E+01 7.0000E+01 8.2000E+00 5.3000E+00 7.7000E+004000200200035 1.6500E+03 1.0000E+02 1.3600E+02 8.2000E+00 5.3000E+00 7.7000E+004000200200036 2.0700E+03 7.2000E+01 7.2000E+01 6.6000E+00 5.7000E+00 8.0000E+004000200200037 2.6200E+03 7.6000E+01 7.6000E+01 5.5000E+00 5.7000E+00 8.0000E+004000200200038 3.1260E+03 6.6000E+01 6.6000E+01 5.3000E+00 6.3000E+00 8.5000E+004000200200039 3.6280E+03 5.5000E+01 5.5000E+01 6.1000E+00 5.7000E+00 8.0000E+004000200200040 ENDDATA 29 0 4000200200041 ENDSUBENT 40 0 4000200299999 ENDENTRY 2 0 4000299999999