ENTRY 41770 20240422 421741770000 1 SUBENT 41770001 20240422 421741770001 1 BIB 8 19 41770001 2 TITLE The study of delayed neutrons emitted by uranium-233 41770001 3 as a result of irradiation by thermal neutron 41770001 4 COMMENT Of compiler M.M. 41770001 5 In title of this article Engl. version there is an 41770001 6 inaccurate translation from the Russian version of this41770001 7 article. More accurate translation is: 41770001 8 Study of delayed neutrons of U-233 after thermal 41770001 9 neutron irradiation. 41770001 10 AUTHOR (S.V.Girshfeld) 41770001 11 INSTITUTE (4RUSRUS) 41770001 12 REFERENCE (C,55GENEVA,4,171,1955) Paper 648. 41770001 13 In Russian publication - page 207. 41770001 14 Page 127 in volume "Fizicheskie Issledovaniya", 41770001 15 doklady Sovetskoy delegatsii na 55GENEVA, 41770001 16 published at 1955, Moscow. 41770001 17 FACILITY (REAC,4RUSRUS) 41770001 18 DETECTOR (BF3) BF3 counter inside paraffin block protected by 41770001 19 Cd layer and boron acid layer. 41770001 20 HISTORY (20240422C) M.M. 41770001 21 ENDBIB 19 0 41770001 22 NOCOMMON 0 0 41770001 23 ENDSUBENT 22 0 4177000199999 SUBENT 41770002 20240422 421741770002 1 BIB 7 8 41770002 2 REACTION (92-U-233(N,F),DL,NU) 41770002 3 INC-SOURCE (THCOL) 41770002 4 INC-SPECT Thermal neutrons 41770002 5 SAMPLE 12 g of U-233. 41770002 6 METHOD (ACTIV) Irradiation at thermal column 41770002 7 ANALYSIS (DECAY) 41770002 8 STATUS (TABLE,,S.V.Girshfel'd,C,55GENEVA,4,171,1955) 41770002 9 Text page 171. 41770002 10 ENDBIB 8 0 41770002 11 NOCOMMON 0 0 41770002 12 DATA 2 1 41770002 13 EN-DUMMY DATA-APRX 41770002 14 EV PC/FIS 41770002 15 0.0253 0.25 41770002 16 ENDDATA 3 0 41770002 17 ENDSUBENT 16 0 4177000299999 SUBENT 41770003 20240422 421741770003 1 BIB 9 12 41770003 2 REACTION (92-U-233(N,F),DL/GRP,NU) 41770003 3 MONITOR (92-U-235(N,F),DL/GRP,NU) 41770003 4 MONIT-REF (,D.J.Hughes+,J,PR,73,111,1948) 41770003 5 #doi:10.1103/PhysRev.73.111 41770003 6 SAMPLE 58.9 mg of U-233. 33.2 mg U-235. 41770003 7 INC-SOURCE (REAC) 41770003 8 INC-SPECT Thermal neutrons 41770003 9 METHOD (ACTIV) Irradiation near wall of reactor 41770003 10 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 41770003 11 article. 41770003 12 STATUS (TABLE,,S.V.Girshfel'd,C,55GENEVA,4,171,1955) 41770003 13 Tables 1, 2 41770003 14 ENDBIB 12 0 41770003 15 COMMON 1 3 41770003 16 EN-DUMMY 41770003 17 EV 41770003 18 0.0253 41770003 19 ENDCOMMON 3 0 41770003 20 DATA 7 5 41770003 21 HL HL-ERR DATA DATA-ERR DATA-MAX MONIT 41770003 22 MONIT-ERR 41770003 23 SEC SEC PC/FIS PC/FIS PC/FIS PC/FIS 41770003 24 PC/FIS 41770003 25 55.3 0.9 0.023 0.0020 0.025 41770003 26 0.0018 41770003 27 22.2 0.2 0.074 0.0058 0.166 41770003 28 0.0116 41770003 29 4.5 0.04 0.094 0.0093 0.213 41770003 30 0.020 41770003 31 1.5 0.07 0.067 0.0078 0.241 41770003 32 0.0212 41770003 33 0.43 0.02 0.085 41770003 34 0.0101 41770003 35 ENDDATA 14 0 41770003 36 ENDSUBENT 35 0 4177000399999 SUBENT 41770004 20240422 421741770004 1 BIB 7 9 41770004 2 REACTION (92-U-233(N,F),DL,NU) 41770004 3 SAMPLE 58.9 mg of U-233. 33.2 mg U-235. 41770004 4 INC-SOURCE (REAC) 41770004 5 INC-SPECT Thermal neutrons 41770004 6 METHOD (ACTIV) Irradiation near wall of reactor 41770004 7 ANALYSIS (DECAY) 41770004 8 STATUS (TABLE,,S.V.Girshfel'd,C,55GENEVA,4,171,1955) 41770004 9 Text page 173. 41770004 10 (DEP,41770003) Group yields 41770004 11 ENDBIB 9 0 41770004 12 NOCOMMON 0 0 41770004 13 DATA 2 1 41770004 14 EN-DUMMY DATA-APRX 41770004 15 EV PC/FIS 41770004 16 0.0253 0.258 41770004 17 ENDDATA 3 0 41770004 18 ENDSUBENT 17 0 4177000499999 ENDENTRY 4 0 4177099999999