ENTRY 40695 20231016 4069500000001 SUBENT 40695001 20231016 20240316 4069500100001 BIB 8 20 4069500100002 TITLE Use of gamma spectrometry to measure the ratio between 4069500100003 the capture and fission cross sections of U238 4069500100004 AUTHOR (L.N.Yurova,A.V.Bushuev) 4069500100005 REFERENCE (J,SJA,20,75,1966) Engl.translation of AE,20,60,1966 4069500100006 (J,AE,20,60,1966) Issue 1. 4069500100007 INSTITUTE (4RUSMIF,4RUSFEI) 4069500100008 FACILITY (REAC,4RUSFEI) Reactor BR-1 4069500100009 CORRECTION For backgrounds. 4069500100010 For spectrometer detection efficiency. 4069500100011 For gamma-ray absorption in samples. 4069500100012 ERR-ANALYS (ERR-S) Statistical uncertainty - 0.5 % . 4069500100013 (DATA-ERR) Type of uncertainty is not explained in the 4069500100014 article. 4069500100015 HISTORY (19840213T) Converted from ENTRY 80091 4069500100016 (20231016A) BIB information was updated. 4069500100017 Upper -> lower case correction. 4069500100018 Dates were corrected for 4-digits year. 4069500100019 4CCPCCP -> 4RUSMIF. 4069500100020 EN-DUMMY : 0.0253 eV -> 1.MeV (fast neutrons of BR-1),4069500100021 MXW -> FST. 4069500100022 ENDBIB 20 0 4069500100023 COMMON 1 3 4069500100024 ERR-S 4069500100025 PER-CENT 4069500100026 0.5 4069500100027 ENDCOMMON 3 0 4069500100028 ENDSUBENT 27 0 4069500199999 SUBENT 40695002 20231016 20240316 4069500200001 BIB 10 15 4069500200002 REACTION (92-U-238(N,ABS),,ALF,,FST) 4069500200003 INC-SPECT Fast neutrons of BR-1 reactor. 4069500200004 SAMPLE 4.7 mg/mm2 thickness. 4069500200005 DETECTOR (SCIN) Scintillation spectrometer with NaI(Tl) crystal 4069500200006 and 100-channel pulse amplitude analyzer. 4069500200007 Cs-137,Au-198,Hg-203, Ce-144+Pr-144, Na-22 sources were4069500200008 used for calibration - photo-efficiency versus 4069500200009 gamma-energy. 4069500200010 DECAY-DATA (92-U-239,,DG,74.,0.435) 43.5 +- 3.0 % 4069500200011 (93-NP-239,,DG,106.,0.504) 50.4 +- 2.5 % 4069500200012 MONITOR (92-U-238(N,F)57-LA-140,CUM,FY) 4069500200013 DECAY-MON (57-LA-140,,DG,1600.,0.94) 4069500200014 ANALYSIS See formula (1) in the article 4069500200015 STATUS (TABLE,,L.N.Yurova+,J,SJA,20,75,1966) Table of page 76 4069500200016 HISTORY (20231016A) MONIT-ERR: PER-CENT -> PC/FIS 4069500200017 ENDBIB 15 0 4069500200018 NOCOMMON 0 0 4069500200019 DATA 5 1 4069500200020 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR 4069500200021 MEV NO-DIM NO-DIM PC/FIS PC/FIS 4069500200022 1.0 0.44 0.04 5.8 0.4 4069500200023 ENDDATA 3 0 4069500200024 ENDSUBENT 23 0 4069500299999 SUBENT 40695003 20231016 20240316 4069500300001 BIB 8 24 4069500300002 REACTION (92-U-238(N,ABS),,ALF,,FST) 4069500300003 INC-SPECT Fast neutron flux of BR-1 reactor. 4069500300004 Thermal spectrum - for normalization. 4069500300005 SAMPLE Natural. U-235 content 0.726 %. 4069500300006 DETECTOR (SCIN) Scintillation spectrometer with NaI(Tl) crystal 4069500300007 and 100-channel pulse amplitude analyzer. 4069500300008 Cs-137,Au-198,Hg-203, Ce-144+Pr-144, Na-22 sources were4069500300009 used for calibration - photo-efficiency versus 4069500300010 gamma-energy. 4069500300011 MONITOR (92-U-235(N,F),,SIG,,MXW) Averaged over Maxwellian 4069500300012 velocity spectrum of thermal neutrons. 4069500300013 (92-U-238(N,G)92-U-239,,SIG,,MXW) Averaged over 4069500300014 Maxwellian velocity spectrum of thermal neutrons. 4069500300015 (92-U-238(N,F)57-LA-140,CUM,FY,,MXW) 4069500300016 For thermal neutrons. 4069500300017 (92-U-235(N,F)57-LA-140,CUM,FY,,MXW) 4069500300018 For thermal neutrons. 4069500300019 . Monitor values are not given in the article. 4069500300020 DECAY-MON (57-LA-140,,DG,1600.,0.94) 4069500300021 ANALYSIS See formula (2) in the article. 4069500300022 La-140 yields for fission of U-235 and U-238 by 4069500300023 neutrons with energies up to 10 MeV are practically 4069500300024 constant. 4069500300025 STATUS (TABLE,,L.N.Yurova+,J,SJA,20,75,1966) Table of page 76 4069500300026 ENDBIB 24 0 4069500300027 COMMON 1 3 4069500300028 EN-NRM 4069500300029 EV 4069500300030 0.0253 4069500300031 ENDCOMMON 3 0 4069500300032 DATA 3 1 4069500300033 EN-DUMMY DATA DATA-ERR 4069500300034 MEV NO-DIM NO-DIM 4069500300035 1.0 0.42 0.03 4069500300036 ENDDATA 3 0 4069500300037 ENDSUBENT 36 0 4069500399999 ENDENTRY 3 0 4069599999999