ENTRY 40031 20201020 41934003100000001 SUBENT 40031001 20201020 41934003100100001 BIB 12 38 4003100100002 INSTITUTE (4RUSEPA) 4003100100003 REFERENCE (J,YF,14,73,1971) Iss.1 4003100100004 (J,SNP,14,41,1972) Engl.translation 4003100100005 Main reference. 4003100100006 Curves of incident spectra and data tables are given 4003100100007 AUTHOR (E.F.Fomushkin,E.K.Gutnikova,A.N.Maslov,G.F.Novoselov, 4003100100008 V.I.Panin) 4003100100009 TITLE Neutron-fission cross sections of Bk249 and Cf249 4003100100010 SAMPLE Films of U-235 monitor samples, U-235 content is 90.0 %4003100100011 and its amount is (1.640+-0.025)*10**15 nuclei 4003100100012 METHOD (FISCT) Direct counting of fission fragments 4003100100013 DETECTOR (TRD) Dielectric track detector with: 4003100100014 polycarbonate thin film of 10.E4 molecular weight - 4003100100015 for measurements by monoenergetic neutrons; 4003100100016 silicate glass plates - for measurements by thermal 4003100100017 and fast reactor neutrons. 4003100100018 Detection efficiency ~12.86 % for isotropic angular 4003100100019 distribution. 4003100100020 MONITOR (92-U-235(N,F),,SIG) 4003100100021 PART-DET (FF) 4003100100022 DECAY-DATA (98-CF-249,345.YR,A)) 345.+-15 yr 4003100100023 (97-BK-249,314.D,B-) 314+-8 d; 4003100100024 Bk-249 alpha decay half-life (5.93+-0.36)*10**4 yr. 4003100100025 ALPHA/BETA=(1.45+-0.08)*10**-5 . 4003100100026 Half-lives used for determination of nuclei amount in 4003100100027 samples. 4003100100028 CORRECTION For background of scattered neutrons < 1.5%; 4003100100029 for effect of evaporated neutrons for U235 at 4003100100030 En=3.0 MeV - ~3-5 %, 4003100100031 for impurities in samples (Cf-249 in Bk-249 sample, 4003100100032 assuming fis.C-S 2.2 b at En= 1.5 , 3.0 MeV) <1.5%. 4003100100033 HISTORY (19771125C) Compiled at the centre - CJD 4003100100034 (20040723A) Date is corrected, 4003100100035 Reaction Code of 007 and 008 Subentries was corrected 4003100100036 (20040818U) Last checking has been done. 4003100100037 (20201020A) Ref. SNP,14,41,1972 was added. 4003100100038 Subents 007,008 were corrected 4003100100039 STATUS information was updated. 4003100100040 ENDBIB 38 0 4003100100041 NOCOMMON 0 0 4003100100042 ENDSUBENT 41 0 4003100199999 SUBENT 40031002 20201020 41934003100200001 BIB 6 11 4003100200002 REACTION (97-BK-249(N,F),,SIG) 4003100200003 FACILITY (VDG) 4003100200004 INC-SOURCE (P-T) 4003100200005 (D-T) 4003100200006 SAMPLE Bk layer, amount of Bk-249 (2.19+-0.13)*10**15 nuclei, 4003100200007 Cf-249 content in Bk-249 sample is 8.0 % 4003100200008 and Cf-252 content is 4.0E-6 % 4003100200009 ERR-ANALYS (EN-ERR) Error in neutron energy of a beam - 4003100200010 total energy spread. 4003100200011 (DATA-ERR) Mainly due to half-lives and statistics. 4003100200012 STATUS (TABLE) From Table 2 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100200013 ENDBIB 11 0 4003100200014 COMMON 1 3 4003100200015 EN-ERR 4003100200016 KEV 4003100200017 100. 4003100200018 ENDCOMMON 3 0 4003100200019 DATA 3 3 4003100200020 EN DATA DATA-ERR 4003100200021 MEV B B 4003100200022 1.5 1.21 9.E-02 4003100200023 3.0 1.34 1.E-01 4003100200024 14.5 2.65 2.E-01 4003100200025 ENDDATA 5 0 4003100200026 ENDSUBENT 25 0 4003100299999 SUBENT 40031003 20201020 41934003100300001 BIB 7 9 4003100300002 REACTION (97-BK-249(N,F),,SIG,,FST) 4003100300003 FACILITY (REAC) Fast reactor 4003100300004 INC-SOURCE (REAC) Fast reactor 4003100300005 SAMPLE Bk layer, amount of Bk-249 (2.19+-0.13)*10**15 nuclei, 4003100300006 Cf-249 content in Bk-249 sample is 8.0 % 4003100300007 and Cf-252 content is 4.0E-6 % 4003100300008 ERR-ANALYS (DATA-ERR) Mainly due to half-lives and statistics. 4003100300009 STATUS (TABLE) From Table 2 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100300010 HISTORY (20201020A) MONIT was added. 4003100300011 ENDBIB 9 0 4003100300012 COMMON 1 3 4003100300013 EN-DUMMY 4003100300014 MEV 4003100300015 1. 4003100300016 ENDCOMMON 3 0 4003100300017 DATA 3 1 4003100300018 DATA DATA-ERR MONIT 4003100300019 B B B 4003100300020 0.75 0.06 1.27 4003100300021 ENDDATA 3 0 4003100300022 ENDSUBENT 21 0 4003100399999 SUBENT 40031004 20201020 41934003100400001 BIB 7 10 4003100400002 REACTION (98-CF-249(N,F),,SIG) 4003100400003 FACILITY (VDG) 4003100400004 INC-SOURCE (D-T) 4003100400005 SAMPLE Layer of Cf, Cf-249 content is (0.353+-0.015)*10**15 4003100400006 and (1.28+-0.06)*10**15 nuclei 4003100400007 CORRECTION Cf-252 content in samples is 2.0E-5 per-cent 4003100400008 ERR-ANALYS (EN-ERR) Error in neutron energy of a beam - 4003100400009 total energy spread. 4003100400010 (DATA-ERR) Mainly due to half-lives and statistics. 4003100400011 STATUS (TABLE) From Table 2 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100400012 ENDBIB 10 0 4003100400013 NOCOMMON 0 0 4003100400014 DATA 4 1 4003100400015 EN EN-ERR DATA DATA-ERR 4003100400016 MEV KEV B B 4003100400017 14.5 100. 2.87 0.21 4003100400018 ENDDATA 3 0 4003100400019 ENDSUBENT 18 0 4003100499999 SUBENT 40031005 20201020 41934003100500001 BIB 9 14 4003100500002 REACTION (98-CF-249(N,F),,SIG,,MXW) 4003100500003 FACILITY (REAC) Thermal reactor 4003100500004 INC-SOURCE (REAC) 4003100500005 INC-SPECT Neutron temperature= 320. degrees Kelvin. 4003100500006 Cd difference was measured with stat. accuracy ~2.%. 4003100500007 SAMPLE Layer of Cf, Cf-249 content is (0.353+-0.015)*10**15 4003100500008 and (1.28+-0.06)*10**15 nuclei 4003100500009 MONITOR ((MONIT)92-U-235(N,F),,SIG) 4003100500010 ERR-ANALYS (DATA-ERR) Mainly due to half-lives and statistics. 4003100500011 STATUS (TABLE) From Table 2 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100500012 HISTORY (20201020A) MONIT was added. 4003100500013 EN-DUMMY=2.53E-02 eV -> KT-K=320 DEG-K according to 4003100500014 a comment of N.Otsuka (NDS, IAEA). 4003100500015 DEG-K -> K. 4003100500016 ENDBIB 14 0 4003100500017 COMMON 1 3 4003100500018 KT-K 4003100500019 K 4003100500020 320. 4003100500021 ENDCOMMON 3 0 4003100500022 DATA 3 1 4003100500023 DATA DATA-ERR MONIT 4003100500024 B B B 4003100500025 1630. 100. 577. 4003100500026 ENDDATA 3 0 4003100500027 ENDSUBENT 26 0 4003100599999 SUBENT 40031006 20201020 41934003100600001 BIB 6 7 4003100600002 REACTION (98-CF-249(N,F),,SIG,,FST) 4003100600003 FACILITY (REAC) Fast reactor 4003100600004 INC-SOURCE (REAC) Fast reactor 4003100600005 SAMPLE Layer of Cf, Cf-249 content is (0.353+-0.015)*10**15 4003100600006 and (1.28+-0.06)*10**15 nuclei 4003100600007 ERR-ANALYS (DATA-ERR) Mainly due to half-lives and statistics. 4003100600008 STATUS (TABLE) From Table 2 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100600009 ENDBIB 7 0 4003100600010 COMMON 1 3 4003100600011 EN-DUMMY 4003100600012 MEV 4003100600013 1. 4003100600014 ENDCOMMON 3 0 4003100600015 DATA 3 1 4003100600016 DATA DATA-ERR MONIT 4003100600017 B B B 4003100600018 2.01 0.13 1.27 4003100600019 ENDDATA 3 0 4003100600020 ENDSUBENT 19 0 4003100699999 SUBENT 40031007 20201020 41934003100700001 BIB 7 16 4003100700002 REACTION (97-BK-249(N,F),,DA,FF,RSD) 4003100700003 FACILITY (VDG) 4003100700004 INC-SOURCE (P-T) 4003100700005 (D-T) 4003100700006 ANALYSIS Angular anisotropy was determined as 4003100700007 (a0+a2)/(a0-0.5*a2), where a0, a2 - coefficients of 4003100700008 Legendre polynomials P in angular distribution 4003100700009 a0+a2*P2(cos(angle)). 4003100700010 ERR-ANALYS (EN-ERR) Error in neutron energy of a beam - 4003100700011 total energy spread. 4003100700012 (DATA-ERR) Mainly due to statistics and geometrical 4003100700013 factors. 4003100700014 STATUS (TABLE) From Table 3 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100700015 HISTORY (20040817A)Reaction code was corrected 4003100700016 (20040818U) Last checking has been done. 4003100700017 (20201020A) PRE code was deleted from SF5 4003100700018 ENDBIB 16 0 4003100700019 COMMON 1 3 4003100700020 ANG 4003100700021 ADEG 4003100700022 0. 4003100700023 ENDCOMMON 3 0 4003100700024 DATA 4 3 4003100700025 EN EN-ERR DATA DATA-ERR 4003100700026 MEV KEV NO-DIM NO-DIM 4003100700027 1.5 100. 1.072 1.8E-02 4003100700028 3. 100. 1.035 1.2E-02 4003100700029 14.5 100. 1.082 1.1E-02 4003100700030 ENDDATA 5 0 4003100700031 ENDSUBENT 30 0 4003100799999 SUBENT 40031008 20201020 41934003100800001 BIB 7 15 4003100800002 REACTION (98-CF-249(N,F),,DA,FF,RSD) 4003100800003 FACILITY (VDG) 4003100800004 INC-SOURCE (D-T) 4003100800005 ANALYSIS Angular anisotropy was determined as 4003100800006 (a0+a2)/(a0-0.5*a2), where a0, a2 - coefficients of 4003100800007 Legendre polynomials P in angular distribution 4003100800008 a0+a2*P2(cos(angle)). 4003100800009 ERR-ANALYS (EN-ERR) Error in neutron energy of a beam - 4003100800010 total energy spread. 4003100800011 (DATA-ERR) Mainly due to statistics and geometrical 4003100800012 factors. 4003100800013 STATUS (TABLE) From Table 3 of Sov.Nucl.Phys.,v.14,p.41,1972 4003100800014 HISTORY (20040817A) Reaction code was corrected 4003100800015 (20040818U) Last checking has been done. 4003100800016 (20201020A) PRE code was deleted from SF5 4003100800017 ENDBIB 15 0 4003100800018 COMMON 1 3 4003100800019 ANG 4003100800020 ADEG 4003100800021 0. 4003100800022 ENDCOMMON 3 0 4003100800023 DATA 4 1 4003100800024 EN EN-ERR DATA DATA-ERR 4003100800025 MEV KEV NO-DIM NO-DIM 4003100800026 14.5 100. 1.095 1.5E-02 4003100800027 ENDDATA 3 0 4003100800028 ENDSUBENT 27 0 4003100899999 ENDENTRY 8 0 4003199999999