ENTRY 40695 20231016 421540695 0 1 SUBENT 40695001 20231016 421540695 1 1 BIB 8 20 40695 1 2 TITLE Use of gamma spectrometry to measure the ratio between 40695 1 3 the capture and fission cross sections of U238 40695 1 4 AUTHOR (L.N.Yurova,A.V.Bushuev) 40695 1 5 REFERENCE (J,SJA,20,75,1966) Engl.translation of AE,20,60,1966 40695 1 6 (J,AE,20,60,1966) Issue 1. 40695 1 7 INSTITUTE (4RUSMIF,4RUSFEI) 40695 1 8 FACILITY (REAC,4RUSFEI) Reactor BR-1 40695 1 9 CORRECTION For backgrounds. 40695 1 10 For spectrometer detection efficiency. 40695 1 11 For gamma-ray absorption in samples. 40695 1 12 ERR-ANALYS (ERR-S) Statistical uncertainty - 0.5 % . 40695 1 13 (DATA-ERR) Type of uncertainty is not explained in the 40695 1 14 article. 40695 1 15 HISTORY (19840213T) Converted from ENTRY 80091 40695 1 16 (20231016A) BIB information was updated. 40695 1 17 Upper -> lower case correction. 40695 1 18 Dates were corrected for 4-digits year. 40695 1 19 4CCPCCP -> 4RUSMIF. 40695 1 20 EN-DUMMY : 0.0253 eV -> 1.MeV (fast neutrons of BR-1),40695 1 21 MXW -> FST. 40695 1 22 ENDBIB 20 0 40695 1 23 COMMON 1 3 40695 1 24 ERR-S 40695 1 25 PER-CENT 40695 1 26 0.5 40695 1 27 ENDCOMMON 3 0 40695 1 28 ENDSUBENT 27 0 40695 199999 SUBENT 40695002 20231016 421540695 2 1 BIB 10 15 40695 2 2 REACTION (92-U-238(N,ABS),,ALF,,FST) 40695 2 3 INC-SPECT Fast neutrons of BR-1 reactor. 40695 2 4 SAMPLE 4.7 mg/mm2 thickness. 40695 2 5 DETECTOR (SCIN) Scintillation spectrometer with NaI(Tl) crystal 40695 2 6 and 100-channel pulse amplitude analyzer. 40695 2 7 Cs-137,Au-198,Hg-203, Ce-144+Pr-144, Na-22 sources were40695 2 8 used for calibration - photo-efficiency versus 40695 2 9 gamma-energy. 40695 2 10 DECAY-DATA (92-U-239,,DG,74.,0.435) 43.5 +- 3.0 % 40695 2 11 (93-NP-239,,DG,106.,0.504) 50.4 +- 2.5 % 40695 2 12 MONITOR (92-U-238(N,F)57-LA-140,CUM,FY) 40695 2 13 DECAY-MON (57-LA-140,,DG,1600.,0.94) 40695 2 14 ANALYSIS See formula (1) in the article 40695 2 15 STATUS (TABLE,,L.N.Yurova+,J,SJA,20,75,1966) Table of page 76 40695 2 16 HISTORY (20231016A) MONIT-ERR: PER-CENT -> PC/FIS 40695 2 17 ENDBIB 15 0 40695 2 18 NOCOMMON 0 0 40695 2 19 DATA 5 1 40695 2 20 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR 40695 2 21 MEV NO-DIM NO-DIM PC/FIS PC/FIS 40695 2 22 1.0 0.44 0.04 5.8 0.4 40695 2 23 ENDDATA 3 0 40695 2 24 ENDSUBENT 23 0 40695 299999 SUBENT 40695003 20231016 421540695 3 1 BIB 8 24 40695 3 2 REACTION (92-U-238(N,ABS),,ALF,,FST) 40695 3 3 INC-SPECT Fast neutron flux of BR-1 reactor. 40695 3 4 Thermal spectrum - for normalization. 40695 3 5 SAMPLE Natural. U-235 content 0.726 %. 40695 3 6 DETECTOR (SCIN) Scintillation spectrometer with NaI(Tl) crystal 40695 3 7 and 100-channel pulse amplitude analyzer. 40695 3 8 Cs-137,Au-198,Hg-203, Ce-144+Pr-144, Na-22 sources were40695 3 9 used for calibration - photo-efficiency versus 40695 3 10 gamma-energy. 40695 3 11 MONITOR (92-U-235(N,F),,SIG,,MXW) Averaged over Maxwellian 40695 3 12 velocity spectrum of thermal neutrons. 40695 3 13 (92-U-238(N,G)92-U-239,,SIG,,MXW) Averaged over 40695 3 14 Maxwellian velocity spectrum of thermal neutrons. 40695 3 15 (92-U-238(N,F)57-LA-140,CUM,FY,,MXW) 40695 3 16 For thermal neutrons. 40695 3 17 (92-U-235(N,F)57-LA-140,CUM,FY,,MXW) 40695 3 18 For thermal neutrons. 40695 3 19 . Monitor values are not given in the article. 40695 3 20 DECAY-MON (57-LA-140,,DG,1600.,0.94) 40695 3 21 ANALYSIS See formula (2) in the article. 40695 3 22 La-140 yields for fission of U-235 and U-238 by 40695 3 23 neutrons with energies up to 10 MeV are practically 40695 3 24 constant. 40695 3 25 STATUS (TABLE,,L.N.Yurova+,J,SJA,20,75,1966) Table of page 76 40695 3 26 ENDBIB 24 0 40695 3 27 COMMON 1 3 40695 3 28 EN-NRM 40695 3 29 EV 40695 3 30 0.0253 40695 3 31 ENDCOMMON 3 0 40695 3 32 DATA 3 1 40695 3 33 EN-DUMMY DATA DATA-ERR 40695 3 34 MEV NO-DIM NO-DIM 40695 3 35 1.0 0.42 0.03 40695 3 36 ENDDATA 3 0 40695 3 37 ENDSUBENT 36 0 40695 399999 ENDENTRY 3 0 4069599999999