ENTRY 40003 20210622 41964000300000001 SUBENT 40003001 20210622 41964000300100001 BIB 13 56 4000300100002 INSTITUTE (4RUSFEI) 4000300100003 REFERENCE (J,AE,21,506,1966) Issue 6. Graph only 4000300100004 (J,SJA,21,1213,1966) English translation of At.Energja 4000300100005 (J,EAF,21,(6),120,1966) French translation of Atomnaja 4000300100006 Energija 4000300100007 (C,66PARIS,1,473,1966) 4000300100008 AUTHOR (V.A.Tolstikov,V.P.Koroleva,V.E.Kolesov,A.G.Dovbenko) 4000300100009 TITLE Radiative capture of fast neutrons by Y89 4000300100010 FACILITY (VDG) Van de Graaff (2.5MeV and 5.0 MeV) 4000300100011 INC-SOURCE (P-LI7) Proton-lithium-7 in neutrons energy range from 4000300100012 0.009 MeV up to 0.3 MeV 4000300100013 (P-T) Proton tritium in energy range of neutrons 4000300100014 from 0.3 MeV to 3.0 MeV 4000300100015 SAMPLE Y(2)0(3) sample 0.640 g/cm**2 thick. 4000300100016 METHOD (ACTIV) 4000300100017 DETECTOR (PROPC) Two end-type beta counters in geometry near 4000300100018 4PI 4000300100019 (FISCH) Fission chamber for registration of U-235 4000300100020 fission events 4000300100021 (LONGC) Long counter for background measurement, 4000300100022 neutron flux monitoring and etc. 4000300100023 MONITOR ((MONIT1)92-U-235(N,F),,SIG) 4000300100024 At thermal energy.See M.D.Goldberg et al. 4000300100025 Neutron cross-section,BNL-325,second edition,suppl.No.24000300100026 v.2A,1966.See Value MONIT1 in COMMON section 4000300100027 ((MONIT2)39-Y-89(N,G)39-Y-90,,SIG) 4000300100028 At thermal energy.See M.D.Goldberg et al. 4000300100029 Neutron cross-section,BNL-325,Second Edition,Suppl.No.24000300100030 v.2A,1966.See value MONIT2 in COMMON section 4000300100031 (92-U-235(N,F),,SIG) 4000300100032 For absolute normalization of cross 4000300100033 section in energy range from 0.3 MeV up to 3.5 MeV 4000300100034 see M.Davey,Nucl.Sci.and Eng.26,149,1966. 4000300100035 For absolute normalization of cross section below 0.3 4000300100036 MeV we used the data of this work above 0.3 MeV 4000300100037 CORRECTION Corrections were introduced 4000300100038 on background of neutrons scattered from material, 4000300100039 of target underlayer and target holder, 4000300100040 on background of neutrons scattered in measuring room, 4000300100041 on background of neutrons from foreign reactions, 4000300100042 on neutrons flux attenuation with distance from target,4000300100043 on 92-U-238 fission, 4000300100044 on deviation of U-235 fission cross-section energy 4000300100045 dependence from 1/v low in thermal neutrons energy 4000300100046 range 4000300100047 ERR-ANALYS (EN-ERR) Energy errors are explained by scatter 4000300100048 of proton energy,final thickness of target,angular 4000300100049 dimensions of irradiated sample and chamber 4000300100050 (ERR-1) Includes error in energy dependence of 4000300100051 measured cross-section,namely statistical errors, 4000300100052 errors in corrections,errors in U-235 fission cross- 4000300100053 sections 4000300100054 (ERR-T) Includes all errors of experiment,errors 4000300100055 of supporting cross sections 4000300100056 HISTORY (19700708C) Data compiled at the centre 4000300100057 (20210622U) M.M. Update for current rules. 4000300100058 ENDBIB 56 0 4000300100059 COMMON 5 3 4000300100060 EN-NRM MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 4000300100061 EV B B B B 4000300100062 2.5300E-02 577.1 0.9 1.28 0.02 4000300100063 ENDCOMMON 3 0 4000300100064 ENDSUBENT 63 0 4000300199999 SUBENT 40003002 20210622 41964000300200001 BIB 3 4 4000300200002 REACTION (39-Y-89(N,G)39-Y-90,,SIG) 4000300200003 DECAY-DATA (39-Y-90-G,64.2HR,B) 4000300200004 STATUS (TABLE) Data received from authors and revised by 4000300200005 V.P.Koroleva for new values of standards (1968) 4000300200006 ENDBIB 4 0 4000300200007 NOCOMMON 0 0 4000300200008 DATA 6 21 4000300200009 EN +EN-ERR -EN-ERR DATA ERR-1 ERR-T 4000300200010 MEV MEV MEV MB PER-CENT PER-CENT 4000300200011 1.6600E-01 5.0000E-01 5.7000E-02 1.2700E+01 7.7000E+00 8.3000E+004000300200012 2.6000E-01 5.3000E-02 6.0000E-02 1.0500E+01 7.6000E+00 8.2000E+004000300200013 2.8000E-01 4.5000E-02 4.5000E-02 1.0500E+01 5.2000E+00 6.0000E+004000300200014 4.5000E-01 5.5000E-02 7.0000E-02 8.9900E+00 7.5000E+00 8.1000E+004000300200015 5.1000E-01 4.3000E-02 4.3000E-02 8.8400E+00 5.4000E+00 6.2000E+004000300200016 6.0700E-01 4.3000E-02 4.3000E-02 8.2600E+00 5.1000E+00 6.0000E+004000300200017 7.0000E-01 7.0000E-02 8.0000E-02 8.0500E+00 7.6000E+00 8.2000E+004000300200018 8.3000E-01 4.3000E-02 4.3000E-02 8.1200E+00 5.6000E+00 6.4000E+004000300200019 9.3700E-01 4.7000E-02 4.7000E-02 7.4400E+00 6.4000E+00 7.1000E+004000300200020 9.6000E-01 7.5000E-02 9.2000E-02 6.1100E+00 7.5000E+00 8.1000E+004000300200021 1.0600E+00 8.0000E-02 1.0000E-01 6.3700E+00 5.8000E+00 6.6000E+004000300200022 1.2400E+00 4.8000E-02 4.8000E-02 5.7400E+00 6.8000E+00 7.4000E+004000300200023 1.3380E+00 4.7000E-02 4.7000E-02 5.4600E+00 5.8000E+00 5.6000E+004000300200024 1.5200E+00 6.0000E-02 6.0000E-02 5.5200E+00 7.2000E+00 7.8000E+004000300200025 1.6800E+00 1.0000E-01 1.3500E-01 5.3200E+00 1.3000E+01 1.3300E+014000300200026 2.0600E+00 6.0000E-02 6.0000E-02 4.2800E+00 9.3000E+00 9.8000E+004000300200027 2.0800E+00 6.3000E-02 6.3000E-02 4.1700E+00 7.2000E+00 7.8000E+004000300200028 2.6100E+00 7.0000E-02 7.0000E-02 4.3000E+00 9.6000E+00 1.0000E+014000300200029 2.6340E+00 7.0000E-02 7.0000E-02 4.4700E+00 7.2000E+00 7.8000E+004000300200030 3.1200E+00 8.0000E-02 8.0000E-02 4.0300E+00 7.2000E+00 7.8000E+004000300200031 3.6200E+00 8.5000E-02 8.5000E-02 3.9500E+00 7.5000E+00 8.1000E+004000300200032 ENDDATA 23 0 4000300200033 ENDSUBENT 32 0 4000300299999 ENDENTRY 2 0 4000399999999