ENTRY 40363 20200929 41914036300000001 SUBENT 40363001 20200929 41914036300100001 BIB 9 24 4036300100002 INSTITUTE (4RUSITE) 4036300100003 REFERENCE (J,SJA,3,729,1957) Eng.transl.of AE,3,(7),11,1957 4036300100004 (J,AE,3,11,1957) Issue 7. 4036300100005 (J,JNE,8,69,1958) Eng.transl.of AE,3,(7),11,1957 4036300100006 AUTHOR (V.K.Gorshkov,R.N.Ivanov,G.M.Kukavadze, 4036300100007 I.A.Reformatsky) 4036300100008 TITLE The yield of U-235 fission products in the rare-earth 4036300100009 region 4036300100010 FACILITY (REAC,4RUSITE) 4036300100011 INC-SOURCE (REAC) 4036300100012 METHOD (ASEP) Integral mass-spectrometer method 4036300100013 (CHSEP) After 20-months cooling 4036300100014 DETECTOR Mass spectrograph 4036300100015 HISTORY (19820706C) 4036300100016 (19910128U) Institute code 'CCP' changed to 'ITE' 4036300100017 (20010311A) Date is corrected 4036300100018 (20150210U) SD: Updated to new date formats,lower case.4036300100019 Ref. on Engl.transl. of AE added. DATA-ERR moved to 4036300100020 Subents 2-4. BIB updated. 4036300100021 (20170116A) M.M. Article was checked. 4036300100022 EN -> EN-DUMMY . Subents 006-008 were added. 4036300100023 CHN -> CUM in MONITOR. 4036300100024 (20200929A) Ref. J,JNE,8,69,1958 was added. 4036300100025 Minor correction of free text. 4036300100026 ENDBIB 24 0 4036300100027 COMMON 1 3 4036300100028 MONIT 4036300100029 PC/FIS 4036300100030 3.2 4036300100031 ENDCOMMON 3 0 4036300100032 ENDSUBENT 31 0 4036300199999 SUBENT 40363002 20200929 41914036300200001 BIB 7 7 4036300200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 4036300200003 SAMPLE Uranium enriched by U-235 4036300200004 INC-SPECT Thermal neutrons 4036300200005 MONITOR (92-U-235(N,F)60-ND-146,CUM,FY) 4036300200006 ERR-ANALYS (DATA-ERR) Error is not specified 4036300200007 STATUS (TABLE) Tbl. 1 from At.Energy,v.3,is.7,p.11,1957 4036300200008 HISTORY (20170116A) CHN -> CUM in REACTION 4036300200009 ENDBIB 7 0 4036300200010 COMMON 1 3 4036300200011 EN-DUMMY 4036300200012 EV 4036300200013 0.025 4036300200014 ENDCOMMON 3 0 4036300200015 DATA 4 11 4036300200016 ELEMENT MASS DATA DATA-ERR 4036300200017 NO-DIM NO-DIM PC/FIS PC/FIS 4036300200018 57. 139. 8.2 .8 4036300200019 58. 140. 6.3 .3 4036300200020 58. 142. 5.8 .2 4036300200021 59. 141. 5.6 .3 4036300200022 60. 143. 5.8 .2 4036300200023 60. 144. 5.6 .3 4036300200024 60. 145. 4.0 .1 4036300200025 60. 148. 1.7 .1 4036300200026 60. 150. 0.7 .1 4036300200027 61. 147. 2.9 .4 4036300200028 61. 149. 1.5 .3 4036300200029 ENDDATA 13 0 4036300200030 ENDSUBENT 29 0 4036300299999 SUBENT 40363003 20200929 41914036300300001 BIB 7 11 4036300300002 REACTION (61-PM-147(N,G)61-PM-148,,SIG) 4036300300003 SAMPLE U-235 fission product 4036300300004 DECAY-DATA (61-PM-147,2.6YR) 4036300300005 ANALYSIS Pm-147 neutron absorbtion cross-section was determined 4036300300006 by dividing equation (1) from equation (2) by measured 4036300300007 fission yields of Pm-147 and Nd-146, theier decay 4036300300008 constants, irradiation and cooling times. 4036300300009 ERR-ANALYS (DATA-ERR) Error is not specified 4036300300010 STATUS (TABLE) From the text of At.Energy,v.3,is.7,p.11,1957 4036300300011 HISTORY (20200929A) Reaction was corrected N,ANS -> N,G 4036300300012 according to a comment from NDS, IAEA. 4036300300013 ENDBIB 11 0 4036300300014 NOCOMMON 0 0 4036300300015 DATA 3 1 4036300300016 EN-DUMMY DATA DATA-ERR 4036300300017 EV B B 4036300300018 0.025 90. 20. 4036300300019 ENDDATA 3 0 4036300300020 ENDSUBENT 19 0 4036300399999 SUBENT 40363004 20200929 41914036300400001 BIB 6 11 4036300400002 REACTION (62-SM-147(N,G)62-SM-148,,SIG) 4036300400003 SAMPLE U-235 fission product 4036300400004 ANALYSIS Sm-147 absorbtion cross section was determined by 4036300400005 solving equation (3) simultaneously with other 4036300400006 equations, analogous (1) and (2), using the measured 4036300400007 fission yields of Pm-147 and Sm-147, theier decay 4036300400008 constants, irradiation and cooling times. 4036300400009 ERR-ANALYS (DATA-ERR) Error is not specified 4036300400010 STATUS (TABLE) From the text of At.Energy,v.3,is.7,p.11,1957 4036300400011 HISTORY (20200929A) Reaction was corrected N,ABS -> N,G 4036300400012 according to a comment from NDS, IAEA. 4036300400013 ENDBIB 11 0 4036300400014 NOCOMMON 0 0 4036300400015 DATA 3 1 4036300400016 EN-DUMMY DATA DATA-ERR 4036300400017 EV B B 4036300400018 0.025 1000. 50. 4036300400019 ENDDATA 3 0 4036300400020 ENDSUBENT 19 0 4036300499999 SUBENT 40363005 20200929 41914036300500001 BIB 5 11 4036300500002 REACTION (62-SM-149(N,G)62-SM-150,,SIG) 4036300500003 SAMPLE U-235 fission product 4036300500004 ANALYSIS Sm-149 absorbtion cross section was determined by 4036300500005 solving simultaneously equations, analogous (1) and (2)4036300500006 ,using the measured fission yields of Nd-146 and Sm-1494036300500007 ,theier decay constants, irradiation and cooling times.4036300500008 STATUS (TABLE) From the text of At.Energy,v.3,is.7,p.11,1957 4036300500009 HISTORY (20170116A) M.M. DATA -> DATA-MIN 4036300500010 (20200929A) DATA-ERR was added. 4036300500011 Reaction was corrected N,ANS -> N,G according to a 4036300500012 comment from NDS, IAEA. 4036300500013 ENDBIB 11 0 4036300500014 NOCOMMON 0 0 4036300500015 DATA 3 1 4036300500016 EN-DUMMY DATA-MIN DATA-ERR 4036300500017 EV B B 4036300500018 0.025 58000. 9000. 4036300500019 ENDDATA 3 0 4036300500020 ENDSUBENT 19 0 4036300599999 SUBENT 40363006 20200929 41914036300600001 BIB 6 9 4036300600002 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 4036300600003 2(92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 4036300600004 Sum of yields was normalized to 100% . 4036300600005 SAMPLE Uranium enriched by U-235 4036300600006 METHOD 1 Measurement with the mass spectrograph 4036300600007 2 Measurement with the mass spectrometer MS-1 4036300600008 INC-SPECT Thermal neutrons 4036300600009 ERR-ANALYS (DATA-ERR) Error is not specified 4036300600010 STATUS (TABLE) Tbl. 2 from At.Energy,v.3,is.7,p.11,1957 4036300600011 ENDBIB 9 0 4036300600012 COMMON 2 3 4036300600013 EN-DUMMY ELEMENT 4036300600014 EV NO-DIM 4036300600015 0.025 60. 4036300600016 ENDCOMMON 3 0 4036300600017 DATA 5 6 4036300600018 MASS DATA 1DATA-ERR 1DATA 2DATA-ERR 2 4036300600019 NO-DIM ARB-UNITS ARB-UNITS ARB-UNITS ARB-UNITS 4036300600020 143. 24.8 E-2 0.5 E-2 25.0 E-2 0.1 E-2 4036300600021 144. 28.6 E-2 0.5 E-2 28.5 E-2 0.2 E-2 4036300600022 145. 18.8 E-2 0.3 E-2 18.8 E-2 0.1 E-2 4036300600023 146. 15.5 E-2 0.3 E-2 15.3 E-2 0.1 E-2 4036300600024 148. 8.2 E-2 0.3 E-2 8.3 E-2 0.1 E-2 4036300600025 150. 4.1 E-2 0.2 E-2 4.6 E-2 0.1 E-2 4036300600026 ENDDATA 8 0 4036300600027 ENDSUBENT 26 0 4036300699999 SUBENT 40363007 20200929 41914036300700001 BIB 6 7 4036300700002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,REL) 4036300700003 Sum of yields was normalized to 100% . 4036300700004 SAMPLE Uranium enriched by U-235 4036300700005 METHOD Measurement with the mass spectrograph 4036300700006 INC-SPECT Thermal neutrons 4036300700007 ERR-ANALYS (DATA-ERR) Error is not specified 4036300700008 STATUS (TABLE) Tbl. 3 from At.Energy,v.3,is.7,p.11,1957 4036300700009 ENDBIB 7 0 4036300700010 COMMON 2 3 4036300700011 EN-DUMMY ELEMENT 4036300700012 EV NO-DIM 4036300700013 0.025 62. 4036300700014 ENDCOMMON 3 0 4036300700015 DATA 3 4 4036300700016 MASS DATA DATA-ERR 4036300700017 NO-DIM ARB-UNITS ARB-UNITS 4036300700018 147. 40. E-2 3. E-2 4036300700019 148. 15. E-2 2. E-2 4036300700020 150. 38. E-2 3. E-2 4036300700021 152. 7. E-2 2. E-2 4036300700022 ENDDATA 6 0 4036300700023 ENDSUBENT 22 0 4036300799999 SUBENT 40363008 20200929 41914036300800001 BIB 6 7 4036300800002 REACTION ((92-U-235(N,F)58-CE-140,CUM,FY)/ 4036300800003 (92-U-235(N,F)58-CE-142,CUM,FY)) 4036300800004 SAMPLE Uranium enriched by U-235 4036300800005 METHOD Measurement with the mass spectrograph 4036300800006 INC-SPECT Thermal neutrons 4036300800007 ERR-ANALYS (DATA-ERR) Error is not specified 4036300800008 STATUS (TABLE) Text,page 732 of Sov.At.Energy,v.3,p.729,1957 4036300800009 ENDBIB 7 0 4036300800010 COMMON 1 3 4036300800011 EN-DUMMY 4036300800012 EV 4036300800013 0.025 4036300800014 ENDCOMMON 3 0 4036300800015 DATA 2 1 4036300800016 DATA DATA-ERR 4036300800017 NO-DIM NO-DIM 4036300800018 1.082 0.029 4036300800019 ENDDATA 3 0 4036300800020 ENDSUBENT 19 0 4036300899999 ENDENTRY 8 0 4036399999999