ENTRY 40121 20151009 41724012100000001 SUBENT 40121001 20151009 41724012100100001 BIB 17 58 4012100100002 TITLE Radiation capture of neutrons by U-238 in the 1.2-4.0 4012100100003 MeV range . 4012100100004 AUTHOR (Yu.G.Panitkin,V.A.Tolstikov) 4012100100005 INSTITUTE (4RUSFEI) 4012100100006 REFERENCE (J,SJA,33,893,1972) Engl.transl.of AE,33,782,1972 4012100100007 (J,AE,33,782,197209) Table of data and graph are given 4012100100008 MONITOR ((MONIT1)92-U-238(N,G)92-U-239,,SIG) Taken 4012100100009 from Nucl.Sc.and Eng.,33,24,1968 4012100100010 ((MONIT2)92-U-235(N,F),,SIG) Data taken from (paper 4012100100011 UK-10,UK-USSR Seminar,June,1968.IAER,July 1971) 4012100100012 MONIT-REF ((MONIT1)20362002,H.O.Menlove+,J,NSE,33,24,1968) 4012100100013 ((MONIT2),W.Hart,C,68DUBNA,,(UK-10),1968) 4012100100014 STATUS (TABLE) Data from AE,33,(3),782,1972 4012100100015 FACILITY (VDG,4RUSFEI) Electrostatic accelerator with the 4012100100016 maximum of energy 5 MeV 4012100100017 INC-SOURCE (P-T) T(p,n)He-3 reaction 4012100100018 INC-SPECT Neutron flux was monitored by ionization chamber with 4012100100019 U-235 layer. 4012100100020 METHOD (ACTIV) Activation 4012100100021 PART-DET (G) Gammas 4012100100022 DETECTOR (GELI) Germanium-lithium detector for induced activity 4012100100023 U-239 74-keV gamma-line was measured. 4012100100024 Recording range of gamma-spectrometer and the 4012100100025 resolution of spectrometer were checked at measurement 4012100100026 with the gamma-spectrum of Tm-170. 4012100100027 (IOCH) Ionization chamber for neutron flux. 4012100100028 ANALYSIS For energies above U-238 fission threshold the U-238 4012100100029 fission products were removed by chemical purification 4012100100030 before measurement of induced activity. 4012100100031 CORRECTION Correction for fluctuation of neutron number 4012100100032 background of neutrons scattered in target chamber 4012100100033 was less than 1% 4012100100034 Neutrons emitting from molybdenum backing made 4012100100035 following contributions in counting rate of 4012100100036 fission chamber 30-50%, in induced activity of 4012100100037 the sample 60-80%. 4012100100038 Correction for inelastic scattering of neutrons 4012100100039 on the construction materials and for admixture 4012100100040 of other fissile nuclei was 5-8% calculating 4012100100041 with accuracy 15% 4012100100042 ERR-ANALYS (DATA-ERR) Mean-square error of experiment. 4012100100043 Errors of introduced corrections are taken 4012100100044 into account. 4012100100045 Errors of fission cross-section of U-235 and capture 4012100100046 cross-section of U-238 were not taken into account 4012100100047 (EN-ERR) Sources of this error were accelerator 4012100100048 beam attenuation and dependence of neutron 4012100100049 energy upon the angle of incidence. 4012100100050 HISTORY (19721122C) Compiled at the centre 4012100100051 (19870608U) Obsolete keywords corrected 4012100100052 (19911021U) Corrected transition from Subent 001 to 4012100100053 Subent 002 4012100100054 (20141115A) SD: Updated to new date formats,lower case.4012100100055 Ref. on Engl.transl. of AE added. 4012100100056 (20151009A) M.M. Article was checked, BIB information 4012100100057 was updated in AUTHOR,TITLE,MONITOR,MONIT-REF,INC-SPECT4012100100058 DETECTOR,ANALYSIS. DECAY-DATA was added. 4012100100059 MONIT2 was corrected U-238 -> U-235. 4012100100060 ENDBIB 58 0 4012100100061 NOCOMMON 0 0 4012100100062 ENDSUBENT 61 0 4012100199999 SUBENT 40121002 20151009 41724012100200001 BIB 4 7 4012100200002 REACTION (92-U-238(N,G)92-U-239,,SIG) 4012100200003 SAMPLE Powder of oxide of U-238 4012100200004 at energies higher than fission barrier 4012100200005 of U-238 was made the chemical treatment 4012100200006 of the sample from fission fragments 4012100200007 DECAY-DATA (92-U-239,,DG,74.) 4012100200008 STATUS (TABLE) Tbl. 1 from SJA,33,893 4012100200009 ENDBIB 7 0 4012100200010 COMMON 2 3 4012100200011 EN-NRM MONIT1 4012100200012 KEV MB 4012100200013 24.4 516. 4012100200014 ENDCOMMON 3 0 4012100200015 DATA 5 11 4012100200016 EN EN-ERR DATA DATA-ERR MONIT2 4012100200017 MEV MEV MB MB B 4012100200018 1.2 0.043 94. 2. 1.23 4012100200019 1.3 0.045 82. 1.7 1.24 4012100200020 1.5 0.049 62. 1.5 1.26 4012100200021 1.8 0.054 48. 1. 1.287 4012100200022 2.0 0.057 40. 1. 1.306 4012100200023 2.2 0.061 33. 1. 1.314 4012100200024 2.5 0.067 27. 0.8 1.287 4012100200025 2.8 0.073 22. 0.8 1.257 4012100200026 3.0 0.078 19. 0.8 1.230 4012100200027 3.5 0.094 16. 1.5 1.186 4012100200028 4.0 0.110 13. 1. 1.140 4012100200029 ENDDATA 13 0 4012100200030 ENDSUBENT 29 0 4012100299999 ENDENTRY 2 0 4012199999999