ENTRY 40019 20180223 41784001900000001 SUBENT 40019001 20180223 41784001900100001 BIB 15 51 4001900100002 INSTITUTE (4RUSTIL) 4001900100003 (4RUSFTI) 4001900100004 REFERENCE (J,YF,15,860,1972) Iss.5 4001900100005 (J,SNP,15,482,1972) Engl.translation of YF,15,(5).860 4001900100006 REL-REF (I,,M.G.Pan'yan+,J,PTE,,(4),250,1971) 4001900100007 (I,,K.A.Petrzhak+,J,YF,11,1178,1970) 4001900100008 Details of mass-spectrometer. 4001900100009 (I,,K.A.Petrzhak+,J,SNP,11,654,1970) 4001900100010 Engl.translation of YF,11,1178,1970 4001900100011 AUTHOR (K.A.Petrzhak, M.G.Pan'yan, V.F.Teplykh, 4001900100012 B.M.Aleksandrov) 4001900100013 TITLE Relative yields of xenon isotopes in Np-237 and 4001900100014 Np-238 fission by neutrons. 4001900100015 FACILITY (REAC,4RUSFTI) Reactor of FTI - Ioffe Institute 4001900100016 (SPECM,4RUSFTI) Mass-spectrometer 4001900100017 INC-SOURCE (REAC) 4001900100018 SAMPLE Neptunium-oxide, Pu-239 impurity content is less 1.E-44001900100019 -1.E-5 % of weight. 4001900100020 Two samples of 9.0 mg weight each were heated at 1000-4001900100021 110 deg C, then packed in Al capsules. 4001900100022 1-st samples was irradiated by thermal neutrons of 4001900100023 6.E+13 n/sec/cm*2 neutron beam during 250 hr. 4001900100024 2-nd sample was covered by Cd of 1mm and irradiated 4001900100025 during 500 hr by neutrons of average effective energy 4001900100026 > 0.5 MeV and 6.E+12 n/sec/cm**2. 4001900100027 METHOD (ASEP) Mass-spectrometric method 4001900100028 MONITOR No information 4001900100029 DECAY-DATA (93-NP-237,2.1E+6YR) 4001900100030 (93-NP-238,2.1D) 4001900100031 (94-PU-238,86.4YR) 4001900100032 ASSUMED (ASSUM1,93-NP-237(N,F),,SIG,,MXW) 4001900100033 (ASSUM2,93-NP-237(N,F),,SIG,,SPA) 4001900100034 Fission c-s by thermal and fast neutrons - 0.019 and 4001900100035 0.4 b, respectively. 4001900100036 (ASSUM3,93-NP-238(N,F),,SIG,,MXW) 4001900100037 Fission c-s by thermal neutrons. 4001900100038 (ASSUM4,93-NP-237(N,G)93-NP-238,,SIG,,MXW) 4001900100039 Capture c-s by thermal neutrons. 4001900100040 (ASSUM5,94-PU-238(N,F),,SIG,,MXW) 4001900100041 (ASSUM6,94-PU-238(N,G)94-PU-239,,SIG,,MXW) 450.b 4001900100042 Fission and capture c-s by thermal neutrons. 4001900100043 These data were used in analysis. 4001900100044 STATUS From YF,15,(5),860,197205. 4001900100045 ERR-ANALYS (DATA-ERR) Not specified 4001900100046 HISTORY (19780719C) Compiled at the center 4001900100047 (20101022A) Units were corrected PER-CENT -> ARB-UNITS.4001900100048 ,CHN,FY,,SPA -> ,CUM,FY,,SPA/REL . 4001900100049 EN-DUMMY was moved in Subents. 4001900100050 BIB information was added. 4001900100051 (20180223U) Rel.ref. PTE was corrected. 4001900100052 REL-REF SNP,11,654,1970 was added. 4001900100053 ENDBIB 51 0 4001900100054 COMMON 5 3 4001900100055 ASSUM1 ASSUM2 ASSUM3 ASSUM4 ASSUM5 4001900100056 B B B B B 4001900100057 0.019 0.4 170. 1600. 180. 4001900100058 ENDCOMMON 3 0 4001900100059 ENDSUBENT 58 0 4001900199999 SUBENT 40019002 20101022 41514001900200001 BIB 5 10 4001900200002 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,SPA/REL) 4001900200003 Isotope yield relative to element yield, in per-cents.4001900200004 ANALYSIS The mass range A=131-136 is used for relative yields 4001900200005 definition. 4001900200006 INC-SPECT Reactor neutron spectrum, thermal neutrons and 10-12.%4001900200007 of neutrons with energy above 0.5 MeV 4001900200008 COMMENT Of authors. At Np-237 fission by fast neutrons the 4001900200009 inessential fine structure was found in mass region 4001900200010 131-136. 4001900200011 STATUS (TABLE) Table 2 of YF,15,(5),860,197205. 4001900200012 ENDBIB 10 0 4001900200013 COMMON 2 3 4001900200014 EN-DUMMY ELEMENT 4001900200015 MEV NO-DIM 4001900200016 1. 5.4000E+01 4001900200017 ENDCOMMON 3 0 4001900200018 DATA 3 4 4001900200019 MASS DATA DATA-ERR 4001900200020 NO-DIM ARB-UNITS ARB-UNITS 4001900200021 1.3100E+02 13.8 0.5 4001900200022 1.3200E+02 21.6 0.5 4001900200023 1.3400E+02 33.5 0.9 4001900200024 1.3600E+02 31.1 0.8 4001900200025 ENDDATA 6 0 4001900200026 ENDSUBENT 25 0 4001900299999 SUBENT 40019003 20101022 41514001900300001 BIB 6 15 4001900300002 REACTION 1(93-NP-238(N,F)ELEM/MASS,CUM,FY,,SPA/REL) 4001900300003 Isotope yield relative to element yield, in per-cents.4001900300004 2(93-NP-238(N,F)ELEM/MASS,CUM,FY,,SPA/REL) 4001900300005 Relative yield, corrected on Xe-135(N,G)Xe-136.4001900300006 Isotope yield relative to element yield, in per-cents.4001900300007 ANALYSIS The mass range A=131-136 is used for relative yields 4001900300008 definition. 4001900300009 INC-SPECT Reactor neutron spectrum, thermal neutrons and 4001900300010 12. percent of neutrons with energy above 0.5 MeV 4001900300011 CORRECTION2 Data corrected on XE-135(N,G)XE-136 reaction 4001900300012 COMMENT Of authors. At Np-238 fission by thermal neutrons the 4001900300013 fine structure was found in mass region 131-136, when 4001900300014 the contribution of Xe-135(N,G)Xe-136 was taken into 4001900300015 account. 4001900300016 STATUS (TABLE) Table 2 of YF,15,(5),860,197205. 4001900300017 ENDBIB 15 0 4001900300018 COMMON 2 3 4001900300019 EN-DUMMY ELEMENT 4001900300020 EV NO-DIM 4001900300021 2.5300E-02 5.4000E+01 4001900300022 ENDCOMMON 3 0 4001900300023 DATA 5 4 4001900300024 MASS DATA 1DATA-ERR 1DATA 2DATA-ERR 2 4001900300025 NO-DIM ARB-UNITS ARB-UNITS ARB-UNITS ARB-UNITS 4001900300026 1.3100E+02 12.3 0.5 15.0 0.60 4001900300027 1.3200E+02 18.2 0.6 22.2 0.80 4001900300028 1.3400E+02 28.5 0.60 35.3 0.80 4001900300029 1.3600E+02 40.6 0.90 27.5 0.60 4001900300030 ENDDATA 6 0 4001900300031 ENDSUBENT 30 0 4001900399999 ENDENTRY 3 0 4001999999999