ENTRY 40055 20141114 41674005500000001 SUBENT 40055001 20141114 41674005500100001 BIB 14 63 4005500100002 TITLE cross section for U-233 and U-235 fission by 4005500100003 neutrons with energies between 3 and 800 keV. 4005500100004 AUTHOR (G.V.Gorlov, B.M.Gokhberg, V.M.Morozov, 4005500100005 G.A.Otroshchenko, V.A.Shigin) 4005500100006 INSTITUTE (4RUSKUR) 4005500100007 REFERENCE (J,SJA,6,317,1960) Eng.trans.of AE,6,453,1959 4005500100008 (J,AE,6,(4),453,1959) 4005500100009 FACILITY (VDG,4RUSKUR) Van de Graaff 4005500100010 INC-SOURCE (P-T) Proton-tritium reaction 4005500100011 INC-SPECT Monoenergetic neutrons were obtained at different 4005500100012 angles for proton energies 12000,1400,1600 keV. 4005500100013 REL-REF (M,,G.V.Gorlov+,J,ZTF,26,985,1956) 4005500100014 Details of method. 4005500100015 METHOD Relative dependence of the fission cross section was 4005500100016 measured, then the absolute normalization was done at 4005500100017 a definite neutron energy 270 keV. 4005500100018 DETECTOR (FISCH) Fission chamber 4005500100019 (LONGC) Long counter was used for flux monitoring; 4005500100020 calibrated by H-28 Ra-Be standard source. 4005500100021 MONITOR Standard source for calibration of 4005500100022 flux monitor 4005500100023 CORRECTION Backgrounds: 4005500100024 proton energy 1299 keV : 4005500100025 - for U235 at 10deg (EN=342 keV) - 11%, 4005500100026 at 140deg (EN=3.4keV) - 40%. 4005500100027 - for U333 at 10deg - 11%, 4005500100028 at 140deg - 45%. 4005500100029 proton energy 1400 and 1600 keV - less 10-20% . 4005500100030 ERR-ANALYS (DATA-ERR) Uncertainty of the relative measurement 4005500100031 includes: 4005500100032 * errors in the determination in the number of 4005500100033 fission events in the chamber,including: 4005500100034 - statistical error, 4005500100035 - the error in the computation for the probability 4005500100036 of neutron scattering in the target. 4005500100037 - Other uncertainties : 4005500100038 (ERR-2) Error in the extrapolation of characteristics 4005500100039 of the working U chamber in thermal neutron flux. 4005500100040 (ERR-3) Error associated with the correction for 4005500100041 fragment absorption in the uranium layer. 4005500100042 (ERR-4) Error in the determination of the amount 4005500100043 of U-235 in the layer of natural uranium. 4005500100044 (ERR-1,2.,14.) Uncertainty of neutron flux - usually 4005500100045 2-3 %, for 9 keV - 6%, for 3.4 keV -14.%; 4005500100046 includes: 4005500100047 (DATA-ERR1)Uncertainty of intensity of the standard 4005500100048 neutron source used to define detector efficiency . 4005500100049 The total error in the determination of the absolute 4005500100050 fission cross section is approximately 8% for U-235 and4005500100051 approximately 9% for U233 (except three points: 3.4, 4005500100052 9. and 30 keV). 4005500100053 HISTORY (19700815R) Data were received from author. 4005500100054 (19700917C) Compiled at the centre 4005500100055 (19870123U) minor errors in Subent 001 and others 4005500100056 corrections. ISO-QUANT into REACTION code converted 4005500100057 (20141114U) SD: Updated to new date formats,lower case.4005500100058 Corrections according last EXFOR rules and Dict. 4005500100059 Ref. on Engl. transl. of AE added. INSTITUTE was 4005500100060 corrected (CCPCCP -> RUSKUR). ERR-ANALYS updated. 4005500100061 (20150126A) M.M. Article was checked, BIB information 4005500100062 was updated in TITLE,METHOD,ERR-ANALYS,SAMPLE,ANALYSIS,4005500100063 INC-SPECT,REL-REF,CORRECTION, ASSUMED (Subent 003) were4005500100064 added. 4005500100065 ENDBIB 63 0 4005500100066 COMMON 5 3 4005500100067 DATA-ERR1 ERR-2 ERR-3 ERR-4 EN-NRM 4005500100068 PER-CENT PER-CENT PER-CENT PER-CENT KEV 4005500100069 3.5 1.5 1. 1. 270. 4005500100070 ENDCOMMON 3 0 4005500100071 ENDSUBENT 70 0 4005500199999 SUBENT 40055002 20141114 41674005500200001 BIB 5 15 4005500200002 REACTION (92-U-235(N,F),,SIG) 4005500200003 INC-SPECT Total energy resolution for incident neutrons 4005500200004 at energy 3.4 keV was 0.8keV 4005500200005 at energy 200 keV was 28 keV 4005500200006 at energy 340 keV was 13 keV 4005500200007 at the higher energies of incident neutrons 4005500200008 resolution was changed from 10 up to 40 keV 4005500200009 SAMPLE Thickness ~2 mg/cm2, diameter 50 mm, enrichment ~85% -4005500200010 in relative measurements. 4005500200011 In absolute measurements: 4005500200012 Layer of natural U oxide was deposited on Al foil. 4005500200013 Thickness ~1.1mg/cm2 and ~0.3 mg/cm2 . 4005500200014 ERR-ANALYS (DATA-ERR2) Uncertainty of normalization to absolute 4005500200015 cross section (from authors). 4005500200016 STATUS (TABLE) received from author 1970/08/15 . 4005500200017 ENDBIB 15 0 4005500200018 COMMON 1 3 4005500200019 DATA-ERR2 4005500200020 PER-CENT 4005500200021 8. 4005500200022 ENDCOMMON 3 0 4005500200023 DATA 3 24 4005500200024 EN DATA DATA-ERR 4005500200025 KEV B B 4005500200026 3.4 4.8 0.5 4005500200027 9.0 3.3 0.2 4005500200028 28.5 2.7 0.1 4005500200029 36.0 2.16 0.12 4005500200030 40.0 2.28 0.14 4005500200031 48.0 1.86 0.06 4005500200032 50.0 2.08 0.11 4005500200033 65.0 2.03 0.06 4005500200034 77.5 1.82 0.05 4005500200035 96.0 1.64 0.08 4005500200036 99.0 1.68 0.07 4005500200037 115.0 1.60 0.04 4005500200038 126.0 1.79 0.08 4005500200039 168.5 1.40 0.04 4005500200040 222.0 1.34 0.05 4005500200041 267.0 1.30 0.05 4005500200042 281.0 1.44 0.06 4005500200043 341.0 1.2 0.02 4005500200044 350.0 1.2 0.05 4005500200045 412.0 1.2 0.05 4005500200046 497.0 1.09 0.04 4005500200047 512.0 1.13 0.05 4005500200048 562.0 1.05 0.04 4005500200049 772.0 1.05 0.04 4005500200050 ENDDATA 26 0 4005500200051 ENDSUBENT 50 0 4005500299999 SUBENT 40055003 20141114 41674005500300001 BIB 7 21 4005500300002 REACTION (92-U-233(N,F),,SIG) 4005500300003 ANALYSIS Cross sections were determined using the well-known 4005500300004 ratio of the fission cross sections for these elements 4005500300005 for thermal neutrons: Sig(U-235)/Sig(U-233)=1.10 to 4005500300006 define amount of U233 - at additional irradiation by 4005500300007 subcadmium neutrons. 4005500300008 INC-SPECT Resolution for incident neutrons 4005500300009 at energy 3.4 keV was 0.7 keV 4005500300010 at energy 200 keV was 17 keV 4005500300011 at energy 340 keV was 9.5 keV 4005500300012 at higher energies of incident neutrons 4005500300013 resolution was changed from 10 up to 40 keV 4005500300014 SAMPLE Thickness ~2 mg/cm2, diameter 28 mm, enrichment ~85% - 4005500300015 in relative measurements. 4005500300016 ASSUMED (ASSUM,(92-U-235(N,F),,SIG)/(92-U-233(N,F),,SIG)) 4005500300017 ERR-ANALYS (ASSUM-ERR) the error in the ratio of the fission 4005500300018 cross sections for thermal neutrons in U-233 and U-235 4005500300019 (DATA-ERR2) Uncertainty of normalization to absolute 4005500300020 cross section (from authors). 4005500300021 STATUS (TABLE) received from author 1970/08/15 . 4005500300022 (DEP,40055002) See ANALYSIS 4005500300023 ENDBIB 21 0 4005500300024 COMMON 3 3 4005500300025 DATA-ERR2 ASSUM ASSUM-ERR 4005500300026 PER-CENT NO-DIM PER-CENT 4005500300027 9. 1.10 3. 4005500300028 ENDCOMMON 3 0 4005500300029 DATA 3 24 4005500300030 EN DATA DATA-ERR 4005500300031 KEV B B 4005500300032 3.4 7.6 1.44 4005500300033 9.0 5.4 0.38 4005500300034 28.5 3.5 0.31 4005500300035 36.0 3.01 0.23 4005500300036 40.0 2.70 0.27 4005500300037 48.0 2.76 0.13 4005500300038 50.0 2.86 0.25 4005500300039 65.0 2.94 0.13 4005500300040 77.5 2.57 0.12 4005500300041 96.0 2.2 0.17 4005500300042 99.0 2.30 0.14 4005500300043 115.0 2.47 0.10 4005500300044 126.0 2.64 0.18 4005500300045 168.5 2.27 0.09 4005500300046 222.0 2.40 0.13 4005500300047 267.0 2.20 0.12 4005500300048 281.0 2.65 0.15 4005500300049 341.0 2.22 0.06 4005500300050 350.0 2.20 0.08 4005500300051 412.0 2.15 0.13 4005500300052 497.0 2.10 0.12 4005500300053 512.0 2.04 0.13 4005500300054 562.0 2.00 0.10 4005500300055 772.0 1.85 0.11 4005500300056 ENDDATA 26 0 4005500300057 ENDSUBENT 56 0 4005500399999 ENDENTRY 3 0 4005599999999