ENTRY 41770 20240422 4177000000001 SUBENT 41770001 20240422 20250110 4177000100001 BIB 8 19 4177000100002 TITLE The study of delayed neutrons emitted by uranium-233 4177000100003 as a result of irradiation by thermal neutron 4177000100004 COMMENT Of compiler M.M. 4177000100005 In title of this article Engl. version there is an 4177000100006 inaccurate translation from the Russian version of this4177000100007 article. More accurate translation is: 4177000100008 Study of delayed neutrons of U-233 after thermal 4177000100009 neutron irradiation. 4177000100010 AUTHOR (S.V.Girshfeld) 4177000100011 INSTITUTE (4RUSRUS) 4177000100012 REFERENCE (C,55GENEVA,4,171,1955) Paper 648. 4177000100013 In Russian publication - page 207. 4177000100014 Page 127 in volume "Fizicheskie Issledovaniya", 4177000100015 doklady Sovetskoy delegatsii na 55GENEVA, 4177000100016 published at 1955, Moscow. 4177000100017 FACILITY (REAC,4RUSRUS) 4177000100018 DETECTOR (BF3) BF3 counter inside paraffin block protected by 4177000100019 Cd layer and boron acid layer. 4177000100020 HISTORY (20240422C) M.M. 4177000100021 ENDBIB 19 0 4177000100022 NOCOMMON 0 0 4177000100023 ENDSUBENT 22 0 4177000199999 SUBENT 41770002 20240422 20250110 4177000200001 BIB 7 8 4177000200002 REACTION (92-U-233(N,F),DL,NU) 4177000200003 INC-SOURCE (THCOL) 4177000200004 INC-SPECT Thermal neutrons 4177000200005 SAMPLE 12 g of U-233. 4177000200006 METHOD (ACTIV) Irradiation at thermal column 4177000200007 ANALYSIS (DECAY) 4177000200008 STATUS (TABLE,,S.V.Girshfel'd,C,55GENEVA,4,171,1955) 4177000200009 Text page 171. 4177000200010 ENDBIB 8 0 4177000200011 NOCOMMON 0 0 4177000200012 DATA 2 1 4177000200013 EN-DUMMY DATA-APRX 4177000200014 EV PC/FIS 4177000200015 0.0253 0.25 4177000200016 ENDDATA 3 0 4177000200017 ENDSUBENT 16 0 4177000299999 SUBENT 41770003 20240422 20250110 4177000300001 BIB 9 12 4177000300002 REACTION (92-U-233(N,F),DL/GRP,NU) 4177000300003 MONITOR (92-U-235(N,F),DL/GRP,NU) 4177000300004 MONIT-REF (,D.J.Hughes+,J,PR,73,111,1948) 4177000300005 #doi:10.1103/PhysRev.73.111 4177000300006 SAMPLE 58.9 mg of U-233. 33.2 mg U-235. 4177000300007 INC-SOURCE (REAC) 4177000300008 INC-SPECT Thermal neutrons 4177000300009 METHOD (ACTIV) Irradiation near wall of reactor 4177000300010 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4177000300011 article. 4177000300012 STATUS (TABLE,,S.V.Girshfel'd,C,55GENEVA,4,171,1955) 4177000300013 Tables 1, 2 4177000300014 ENDBIB 12 0 4177000300015 COMMON 1 3 4177000300016 EN-DUMMY 4177000300017 EV 4177000300018 0.0253 4177000300019 ENDCOMMON 3 0 4177000300020 DATA 7 5 4177000300021 HL HL-ERR DATA DATA-ERR DATA-MAX MONIT 4177000300022 MONIT-ERR 4177000300023 SEC SEC PC/FIS PC/FIS PC/FIS PC/FIS 4177000300024 PC/FIS 4177000300025 55.3 0.9 0.023 0.0020 0.025 4177000300026 0.0018 4177000300027 22.2 0.2 0.074 0.0058 0.166 4177000300028 0.0116 4177000300029 4.5 0.04 0.094 0.0093 0.213 4177000300030 0.020 4177000300031 1.5 0.07 0.067 0.0078 0.241 4177000300032 0.0212 4177000300033 0.43 0.02 0.085 4177000300034 0.0101 4177000300035 ENDDATA 14 0 4177000300036 ENDSUBENT 35 0 4177000399999 SUBENT 41770004 20240422 20250110 4177000400001 BIB 7 9 4177000400002 REACTION (92-U-233(N,F),DL,NU) 4177000400003 SAMPLE 58.9 mg of U-233. 33.2 mg U-235. 4177000400004 INC-SOURCE (REAC) 4177000400005 INC-SPECT Thermal neutrons 4177000400006 METHOD (ACTIV) Irradiation near wall of reactor 4177000400007 ANALYSIS (DECAY) 4177000400008 STATUS (TABLE,,S.V.Girshfel'd,C,55GENEVA,4,171,1955) 4177000400009 Text page 173. 4177000400010 (DEP,41770003) Group yields 4177000400011 ENDBIB 9 0 4177000400012 NOCOMMON 0 0 4177000400013 DATA 2 1 4177000400014 EN-DUMMY DATA-APRX 4177000400015 EV PC/FIS 4177000400016 0.0253 0.258 4177000400017 ENDDATA 3 0 4177000400018 ENDSUBENT 17 0 4177000499999 ENDENTRY 4 0 4177099999999