ENTRY 40027 20141109 41674002700000001 SUBENT 40027001 20141109 41674002700100001 BIB 6 18 4002700100002 INSTITUTE (4RUSFEI) 4002700100003 REFERENCE ((R,ICD-4,339,1967)=(R,INDC(CCP)-4,339,1967)) Tables. 4002700100004 (J,AE,24,(2),185,196802) First author Nesterov. 4002700100005 Data of SUBENTs .002 and .003 are presented. 4002700100006 (J,SJA,24,224,1968) Eng.transl.of AE,24,185,1968 4002700100007 AUTHOR (G.N.Smirenkin, V.G.Nesterov) 4002700100008 TITLE Ratios of fast fission cross sections of U-233, U-235, 4002700100009 Pu-239. 4002700100010 STATUS (COREL,40650001) In 40650 - measurement by fission 4002700100011 chamber ( Table III, series I of R,ICD-4,339,1967. 4002700100012 HISTORY (19721001C) 4002700100013 (20080122A) M.M. BIB information was added. 4002700100014 Upper-lower case correction. 4002700100015 (20090729U) Misprints in Status lines of Subents 4002700100016 002,003 were corrected. 4002700100017 (20141109U) SD: Ref. on Engl.transl. of AE added. 4002700100018 (20141223A) M.M. STATUS, R,INDC(CCP)-4,339,1967 were 4002700100019 added. 4002700100020 ENDBIB 18 0 4002700100021 NOCOMMON 0 0 4002700100022 ENDSUBENT 21 0 4002700199999 SUBENT 40027002 20090729 41474002700200001 BIB 11 36 4002700200002 REACTION ((92-U-233(N,F),,SIG)/ 4002700200003 (92-U-235(N,F),,SIG)) 4002700200004 FACILITY (REAC) Fast Reactor BR-5. 4002700200005 Graphite column. Cadmium ratio more 1.E+4. 4002700200006 SAMPLE U-233 oxide with admixtures of 4.99 % U-238, 4002700200007 2.24 % U-234, 0.14 % U-235, 4002700200008 Layer of about 1 mg/cm2 thick. 4002700200009 U-235 90 % enriched . 4002700200010 METHOD Counter ratio 4002700200011 DETECTOR (GLASD) Glass detector 4002700200012 PART-DET (FF) Fission fragments 4002700200013 MONIT-REF (,,R,BNL-325,2,1965) 4002700200014 MONITOR ((92-U-233(N,F),,SIG,,MXW)/(92-U-235(N,F),,SIG,,MXW)) 4002700200015 Reference ratio of Maxwellian spectrum cross 4002700200016 sections are taken for temperature 20 centigrade 4002700200017 from MONIT-REF. 4002700200018 CORRECTION Corrections are made on admixture of strange4002700200019 isotopes (less 4.0 % ), angular anisotropy 4002700200020 of fission(less 1.8 % ), difference of 4002700200021 thermal neutron gas temperature from 20 4002700200022 centigrade. 4002700200023 ERR-ANALYS (ERR-S) Statistical error 1.4 % 4002700200024 (ERR-1) Error of glass scanning 0.5 % 4002700200025 Error connected with admixture of strange 4002700200026 isotope less 0.2 % 4002700200027 Error connected with angular anisotropy 4002700200028 of fission less 0.6 % 4002700200029 Error connected with slow neutron background4002700200030 less 0.3 % 4002700200031 Error connected with neutrons scattered 4002700200032 in the walls of target and detector 4002700200033 less 0.4 % 4002700200034 Error of thermal fission cross sections 4002700200035 ratio less 0.2 % 4002700200036 (ERR-T) Total error (about 2.2 % ) 4002700200037 STATUS (TABLE) Table 1 of Reference R,ICD-4,339,1967. 4002700200038 ENDBIB 36 0 4002700200039 COMMON 2 3 4002700200040 ERR-S ERR-1 4002700200041 PER-CENT PER-CENT 4002700200042 1.4 0.5 4002700200043 ENDCOMMON 3 0 4002700200044 DATA 4 4 4002700200045 EN EN-ERR DATA ERR-T 4002700200046 MEV MEV NO-DIM NO-DIM 4002700200047 4.8500E-01 4.5000E-02 1.6660E+00 3.3000E-02 4002700200048 9.9500E-01 3.5000E-02 1.5840E+00 3.2000E-02 4002700200049 1.3000E+00 3.0000E-02 1.5540E+00 3.2000E-02 4002700200050 2.5050E+00 2.0000E-02 1.5580E+00 3.3000E-02 4002700200051 ENDDATA 6 0 4002700200052 ENDSUBENT 51 0 4002700299999 SUBENT 40027003 20090729 41474002700300001 BIB 11 35 4002700300002 REACTION ((94-PU-239(N,F),,SIG)/ 4002700300003 (92-U-235(N,F),,SIG)) 4002700300004 FACILITY (REAC) Fast Reactor BR-5 . 4002700300005 Graphite column. Cadmium ratio more 1.E+4. 4002700300006 SAMPLE Pu-239 oxide with admixtures of 3.4 % Pu-240. 4002700300007 Layer 1 mg/cm2 thick. 4002700300008 U-235 90 % enriched. 4002700300009 METHOD Counter ratio 4002700300010 DETECTOR (GLASD) Glass detector 4002700300011 PART-DET (FF) Fission fragments 4002700300012 MONIT-REF (,,R,BNL-325,2,1965) 4002700300013 MONITOR ((94-PU-239(N,F),,SIG,,MXW)/(92-U-235(N,F),,SIG,,MXW)) 4002700300014 Reference ratio of maxwellian spectrum cross 4002700300015 sections are taken for temperature 20 centigrade 4002700300016 from MONIT-REF. 4002700300017 CORRECTION Corrections are made on admixture of strange4002700300018 isotopes(less 4.0 % ),angular anisotropy 4002700300019 of fission(less 1.8 % ), difference of 4002700300020 thermal neutron gas temperature from 20 4002700300021 centigrade. 4002700300022 ERR-ANALYS (ERR-S) Statistical error 1.4 % 4002700300023 (ERR-1) Error of glass scanning 0.5 % 4002700300024 Error connected with admixture of strange 4002700300025 isotope less 0.2 % 4002700300026 Error connected with angular anisotropy 4002700300027 of fission less 0.6 % 4002700300028 Error connected with slow neutron background4002700300029 less 0.3 % 4002700300030 Error connected with neutrons scattered 4002700300031 in the walls of target and detector 4002700300032 less 0.4 % 4002700300033 Error of thermal fission cross sections 4002700300034 ratio less 0.5 % 4002700300035 (ERR-T) Total error (about 2.2 % ) 4002700300036 STATUS (TABLE) Table 1 of Reference R,ICD-4,339,1967. 4002700300037 ENDBIB 35 0 4002700300038 COMMON 2 3 4002700300039 ERR-S ERR-1 4002700300040 PER-CENT PER-CENT 4002700300041 1.4 0.5 4002700300042 ENDCOMMON 3 0 4002700300043 DATA 4 3 4002700300044 EN EN-ERR DATA ERR-T 4002700300045 MEV MEV NO-DIM NO-DIM 4002700300046 9.9500E-01 3.5000E-02 1.3720E+00 2.9000E-02 4002700300047 1.8150E+00 2.5000E-02 1.4830E+00 3.2000E-02 4002700300048 2.5050E+00 2.0000E-02 1.5220E+00 3.3000E-02 4002700300049 ENDDATA 5 0 4002700300050 ENDSUBENT 49 0 4002700399999 SUBENT 40027004 20090729 41474002700400001 BIB 8 12 4002700400002 REACTION ((92-U-233(N,F),,SIG)/ 4002700400003 (92-U-235(N,F),,SIG)) 4002700400004 FACILITY (VDG) Van de Graaff accelerator 4002700400005 INC-SOURCE (P-T) T(p,n)He-3 reaction on solid targets of about 4002700400006 (0.3-0.6)mg/cm**2 thickness of tritium-titanium layer.4002700400007 SAMPLE U-233 oxide with admixtures of 4.99 % U-238, 4002700400008 2.24 % U-234, 0.14 % U-235. 4002700400009 DETECTOR (FISCH) Fission chamber 4002700400010 PART-DET (FF) Fission fragments 4002700400011 ERR-ANALYS Statistical errors about 1.-1.5 %, 4002700400012 Total errors less 2.7 % 4002700400013 STATUS (TABLE) Table III of R,ICD-4,339,1967. 4002700400014 ENDBIB 12 0 4002700400015 NOCOMMON 0 0 4002700400016 DATA 3 44 4002700400017 EN EN-ERR DATA 4002700400018 MEV MEV NO-DIM 4002700400019 3.3000E-01 2.5000E-02 1.6330E+00 4002700400020 4.0000E-01 2.3000E-02 1.6340E+00 4002700400021 4.6000E-01 2.3000E-02 1.7230E+00 4002700400022 5.0500E-01 2.2000E-02 1.6930E+00 4002700400023 5.6000E-01 2.2000E-02 1.6750E+00 4002700400024 6.2000E-01 2.1000E-02 1.6450E+00 4002700400025 6.7000E-01 2.1000E-02 1.6690E+00 4002700400026 7.2000E-01 2.0000E-02 1.6610E+00 4002700400027 7.7000E-01 2.0000E-02 1.7260E+00 4002700400028 8.2000E-01 2.0000E-02 1.6630E+00 4002700400029 8.7500E-01 2.0000E-02 1.6340E+00 4002700400030 9.2000E-01 2.0000E-02 1.6190E+00 4002700400031 9.7000E-01 2.0000E-02 1.6240E+00 4002700400032 1.0000E+00 2.0000E-02 1.5780E+00 4002700400033 1.0600E+00 3.4000E-02 1.5620E+00 4002700400034 1.1300E+00 3.3000E-02 1.5510E+00 4002700400035 1.1700E+00 3.2000E-02 1.5440E+00 4002700400036 1.2000E+00 3.2000E-02 1.5640E+00 4002700400037 1.2800E+00 3.1000E-02 1.5590E+00 4002700400038 1.3200E+00 3.0000E-02 1.6190E+00 4002700400039 1.3600E+00 2.9000E-02 1.5200E+00 4002700400040 1.4200E+00 2.9000E-02 1.5090E+00 4002700400041 1.4700E+00 2.8000E-02 1.5320E+00 4002700400042 1.5200E+00 2.8000E-02 1.5200E+00 4002700400043 1.5700E+00 2.7000E-02 1.5120E+00 4002700400044 1.6300E+00 2.7000E-02 1.5140E+00 4002700400045 1.6800E+00 2.6000E-02 1.5060E+00 4002700400046 1.7300E+00 2.6000E-02 1.4970E+00 4002700400047 1.7800E+00 2.5000E-02 1.5180E+00 4002700400048 1.8300E+00 2.5000E-02 1.4720E+00 4002700400049 1.8800E+00 2.4000E-02 1.4370E+00 4002700400050 1.9300E+00 2.4000E-02 1.4970E+00 4002700400051 1.9800E+00 2.4000E-02 1.5230E+00 4002700400052 2.0200E+00 2.3000E-02 1.5030E+00 4002700400053 2.0800E+00 2.3000E-02 1.4990E+00 4002700400054 2.1300E+00 2.3000E-02 1.4810E+00 4002700400055 2.1800E+00 2.2000E-02 1.4820E+00 4002700400056 2.2200E+00 2.2000E-02 1.4570E+00 4002700400057 2.2750E+00 2.2000E-02 1.4250E+00 4002700400058 2.3250E+00 2.1000E-02 1.5140E+00 4002700400059 2.3900E+00 2.1000E-02 1.5130E+00 4002700400060 2.4700E+00 2.0000E-02 1.4880E+00 4002700400061 2.5200E+00 2.0000E-02 1.4940E+00 4002700400062 2.5750E+00 2.0000E-02 1.5340E+00 4002700400063 ENDDATA 46 0 4002700400064 ENDSUBENT 63 0 4002700499999 SUBENT 40027005 20090729 41474002700500001 BIB 9 14 4002700500002 REACTION ((94-PU-239(N,F),,SIG)/ 4002700500003 (92-U-235(N,F),,SIG)) 4002700500004 FACILITY (VDG) Van de Graaff accelerator 4002700500005 INC-SOURCE (P-T) T(p,n)He-3 reaction on solid targets of about 4002700500006 (0.3-0.6)mg/cm**2 thickness of tritium-titanium layer.4002700500007 SAMPLE Pu-239 with 3.4 % Pu-240 . 4002700500008 DETECTOR (FISCH) Fission chamber 4002700500009 PART-DET (FF) Fission fragments 4002700500010 COMMENT Results of this work agree well with Daveys curve 4002700500011 for energy less 0.7 MeV . 4002700500012 Above 0.7MeV results deviate from 7 to 10 %. 4002700500013 ERR-ANALYS Statistical errors about 1.-1.5 %, 4002700500014 Total errors less 2.7 %. 4002700500015 STATUS (TABLE) Table III of R,ICD-4,339,1967. 4002700500016 ENDBIB 14 0 4002700500017 NOCOMMON 0 0 4002700500018 DATA 3 44 4002700500019 EN EN-ERR DATA 4002700500020 MEV MEV NO-DIM 4002700500021 3.3000E-01 2.5000E-02 1.2060E+00 4002700500022 4.4000E-01 2.3000E-02 1.2960E+00 4002700500023 4.6000E-01 2.3000E-02 1.3720E+00 4002700500024 5.0500E-01 2.2000E-02 1.3890E+00 4002700500025 5.6000E-01 2.2000E-02 1.3930E+00 4002700500026 6.2000E-01 2.1000E-02 1.3750E+00 4002700500027 6.7000E-01 2.1000E-02 1.3860E+00 4002700500028 7.2000E-01 2.0000E-02 1.4350E+00 4002700500029 7.7000E-01 2.0000E-02 1.4350E+00 4002700500030 8.2000E-01 2.0000E-02 1.4150E+00 4002700500031 8.7500E-01 2.0000E-02 1.4550E+00 4002700500032 9.2000E-01 2.0000E-02 1.4330E+00 4002700500033 9.7000E-01 2.0000E-02 1.4220E+00 4002700500034 1.0000E+00 2.0000E-02 1.4160E+00 4002700500035 1.0600E+00 3.4000E-02 1.3970E+00 4002700500036 1.1300E+00 3.3000E-02 1.3800E+00 4002700500037 1.1700E+00 3.2000E-02 1.4180E+00 4002700500038 1.2000E+00 3.2000E-02 1.4610E+00 4002700500039 1.2800E+00 3.1000E-02 1.4600E+00 4002700500040 1.3200E+00 3.0000E-02 1.4430E+00 4002700500041 1.3600E+00 2.9000E-02 1.5090E+00 4002700500042 1.4200E+00 2.9000E-02 1.4950E+00 4002700500043 1.4700E+00 2.8000E-02 1.5270E+00 4002700500044 1.5200E+00 2.8000E-02 1.5100E+00 4002700500045 1.5700E+00 2.7000E-02 1.5370E+00 4002700500046 1.6300E+00 2.7000E-02 1.5040E+00 4002700500047 1.6800E+00 2.6000E-02 1.5270E+00 4002700500048 1.7300E+00 2.6000E-02 1.5300E+00 4002700500049 1.7800E+00 2.5000E-02 1.5590E+00 4002700500050 1.8300E+00 2.5000E-02 1.5130E+00 4002700500051 1.8800E+00 2.4000E-02 1.4510E+00 4002700500052 1.9300E+00 2.4000E-02 1.4700E+00 4002700500053 1.9800E+00 2.4000E-02 1.5150E+00 4002700500054 2.0200E+00 2.3000E-02 1.5010E+00 4002700500055 2.0800E+00 2.3000E-02 1.4890E+00 4002700500056 2.1300E+00 2.3000E-02 1.4750E+00 4002700500057 2.1800E+00 2.2000E-02 1.5040E+00 4002700500058 2.2200E+00 2.2000E-02 1.4540E+00 4002700500059 2.2750E+00 2.2000E-02 1.4300E+00 4002700500060 2.3250E+00 2.1000E-02 1.4820E+00 4002700500061 2.3900E+00 2.1000E-02 1.4650E+00 4002700500062 2.4700E+00 2.0000E-02 1.4650E+00 4002700500063 2.5200E+00 2.0000E-02 1.4390E+00 4002700500064 2.5750E+00 2.0000E-02 1.4300E+00 4002700500065 ENDDATA 46 0 4002700500066 ENDSUBENT 65 0 4002700599999 ENDENTRY 5 0 4002799999999