ENTRY 30460 20090311 31353046000000001 SUBENT 30460001 20090311 31353046000100001 BIB 16 40 3046000100002 INSTITUTE (3DDRZFI,4ZZZDUB) 3046000100003 REFERENCE (R,ZFK-341,197709) in German 3046000100004 (C,75KIEV,3,200,197505) Preliminary results, in Russian3046000100005 AUTHOR (K.Dietze) 3046000100006 TITLE Determination of absolute neutron capture cross 3046000100007 sections of uranium-238 by spherical shell transmission3046000100008 measurements 3046000100009 FACILITY (REAC,4ZZZDUB) 3046000100010 (MICRT) 3046000100011 'IBR-30' pulsed reactor with microtron injector 3046000100012 INC-SOURCE (REAC) Transmission measurements were made with 3046000100013 facility working in 'reactor regime'. The 'linear 3046000100014 accelerator regime' was used for methodical checks only3046000100015 SAMPLE Spherical shell targets (thickness from 7.5 to 55 mm) 3046000100016 of U-238 containing 0.35% U-235 3046000100017 METHOD (SHELT) Spherical shell transmission, inverse geometry 3046000100018 (TOF) 3046000100019 DETECTOR (HE3SP) He-3 proportional counters, cylindrical tube 3046000100020 type SNM-50. Reactor-regime= battery of 10 counters 3046000100021 Injector-regime= battery of 91 counters 3046000100022 ANALYSIS Spherical transmissions as a function of the cross 3046000100023 section were calculated by Monte Carlo programs. 3046000100024 Using this curve and the experimental transmission 3046000100025 value, the cross section was determined graphically. 3046000100026 MONITOR Absolute measurement 3046000100027 PART-DET (N) 3046000100028 STATUS (TABLE) Data taken from report ZFK-341, 3046000100029 Sept.1977, Tables 4, 18. 3046000100030 HISTORY (19781208C) OS. 3046000100031 (20090310A) SD:Updated to new date formats,lower case. 3046000100032 CORRECTION Corrections and/or checks have been applied for 3046000100033 -homogeneity and parallelity of neutron beam 3046000100034 -background from different sources (room,spont.fiss.of 3046000100035 U, reactor, recyclyc and scattered neutrons) 3046000100036 -absorption in the detector 3046000100037 -anisotropy of detector efficiency 3046000100038 -influence of detector and target supports 3046000100039 -influence of the U-235 content 3046000100040 -multiple scattering and resonance-selfshielding 3046000100041 ERR-ANALYS (DATA-ERR) Statistical and systematical errors included3046000100042 ENDBIB 40 0 3046000100043 NOCOMMON 0 0 3046000100044 ENDSUBENT 43 0 3046000199999 SUBENT 30460002 20090311 31353046000200001 BIB 1 1 3046000200002 REACTION (92-U-238(N,G)92-U-239,,SIG) 3046000200003 ENDBIB 1 0 3046000200004 NOCOMMON 0 0 3046000200005 DATA 5 2 3046000200006 EN +EN-RSL -EN-RSL DATA DATA-ERR 3046000200007 KEV KEV KEV MB MB 3046000200008 2.4000E+01 2.0000E+00 1.0000E+00 5.0500E+02 3.0000E+01 3046000200009 3.0000E+01 3.0000E+00 2.0000E+00 4.7500E+02 3.0000E+01 3046000200010 ENDDATA 4 0 3046000200011 ENDSUBENT 10 0 3046000299999 SUBENT 30460003 20090311 31353046000300001 BIB 2 7 3046000300002 REACTION (92-U-238(N,G)92-U-239,,SIG,,SPA) 3046000300003 INC-SPECT Effective incoming neutron spectrum (including energy 3046000300004 dependence of detector efficiency) = prop. 1/E**1.4 3046000300005 Data are corrected so that average cross sections given3046000300006 are valid for 1/E reactor spectrum. 3046000300007 The energy boundaries correspond to 'ABBN' 3046000300008 energy groups. 3046000300009 ENDBIB 7 0 3046000300010 NOCOMMON 0 0 3046000300011 DATA 4 8 3046000300012 EN-MIN EN-MAX DATA DATA-ERR 3046000300013 KEV KEV B B 3046000300014 4.6500E+01 1.0000E+02 3.2000E-01 4.0000E-02 3046000300015 2.1500E+01 4.6500E+01 4.8000E-01 3.0000E-02 3046000300016 1.0000E+01 2.1500E+01 5.8000E-01 3.0000E-02 3046000300017 4.6500E+00 1.0000E+01 7.3000E-01 4.0000E-02 3046000300018 2.1500E+00 4.6500E+00 1.2000E+00 6.0000E-02 3046000300019 1.0000E+00 2.1500E+00 1.8500E+00 1.0000E-01 3046000300020 4.6500E-01 1.0000E+00 3.2000E+00 2.0000E-01 3046000300021 2.1500E-01 4.6500E-01 5.7000E+00 6.0000E-01 3046000300022 ENDDATA 10 0 3046000300023 ENDSUBENT 22 0 3046000399999 ENDENTRY 3 0 3046099999999