ENTRY 40206 20151130 41734020600000001 SUBENT 40206001 20151130 41734020600100001 BIB 14 50 4020600100002 TITLE Determination of the yields of certain fragments in 4020600100003 the fission of U-238 by reactor spectrum neutrons 4020600100004 AUTHOR (L.N.Yurova,A.V.Bushuev,A.F.Kozhin) 4020600100005 INSTITUTE (4RUSMIF) 4020600100006 REFERENCE (J,SJA,36,75,1974) Eng.transl.of AE,36,66,1974 4020600100007 (J,AE,36,(1),66,197401) 4020600100008 (C,73KIEV,3,315,197305) 4020600100009 REL-REF (R,,M.A.Wakat,J,ND/A,8,(4-6),445,1971) 4020600100010 (R,,C.M.Lederer+,B,LEDERER-6,,1967) 4020600100011 Two refs. for decay data . 4020600100012 METHOD (ACTIV) Irradiation time 10 hr for FF of HL < 1 month, 4020600100013 80 hr for FF of HL > 1 month. 4020600100014 (GSPEC) Intensity of 1597 keV gamma of La-140 was 4020600100015 measured by NaI(Tl) detector after 12 days cooling. 4020600100016 Gamma spectra of activated foils were measured by GeLi 4020600100017 detector after 2-10 days cooling and after 30-90 days 4020600100018 for long irradiated foils. 4020600100019 FACILITY (REAC,4RUSMIF) Reactor IRT-2000. 4020600100020 INC-SOURCE (REAC) 4020600100021 INC-SPECT - Irradiation at reactor active zone spectrum using the4020600100022 depleted samples with Cd screen and natural samples. 4020600100023 - Irradiation of enriched samples at thermal neutron 4020600100024 spectrum with Cd ratio 45 for U-235 fission. 4020600100025 SAMPLE Foils of 90.% U-235 and depleted ( 200 times)on U-235 4020600100026 DECAY-DATA ((1.)41-NB-95,,DG,764.) 4020600100027 ((2.)41-NB-97,,DG,658.) 4020600100028 ((3.)44-RU-103,,DG,497.) 4020600100029 ((4.)53-I-131,,DG,364.) 4020600100030 ((5.)53-I-132,,DG,668.,,DG,773.) 4020600100031 ((6.)53-I-133,,DG,530.) 4020600100032 ((7.)58-CE-141,,DG,145.4) 4020600100033 ((8.)58-CE-143,,DG,293.) 4020600100034 ((9.)58-CE-144,,DG,134.) 4020600100035 ((10.)60-ND-147,,DG,91.) 4020600100036 (57-LA-140,,DG,1597.) 4020600100037 DETECTOR (NAICR) For number of fission measurement on La-140 4020600100038 (GELI) For yield determination. 4020600100039 Energy resolution 2.0keV for 122 keV gamma of Co-57, 4020600100040 2.9 keV for 662 keV gamma of Cs-137 4020600100041 CORRECTION For gamma-rays self-absorption. 4020600100042 HISTORY (19780720C) Compiled at the centre - CJD 4020600100043 (19911125U) Obsolete keywords changed 4020600100044 data of this entry contain also Rider's 4020600100045 Entry 90615 4020600100046 (20150109A) SD: Updated to new date formats,lower case.4020600100047 Ref. on Engl.transl. of AE added. 4020600100048 (20151130A) M.M. Articles were checked, BIB information4020600100049 was updated in METHOD,STATUS,ERR-ANALYS,INC-SPECT. 4020600100050 CORRECTION, DECAY-DATA,DECAY-FLAG,ASSUMED,ANALYSIS were4020600100051 added. 4020600100052 ENDBIB 50 0 4020600100053 NOCOMMON 0 0 4020600100054 ENDSUBENT 53 0 4020600199999 SUBENT 40206002 20151130 41734020600200001 BIB 7 30 4020600200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 4020600200003 MONITOR (92-U-235(N,F)ELEM/MASS,CUM,FY) From: 4020600200004 W.Walker,R,IAEA-CN-26/3,1970 4020600200005 ANALYSIS Yield of i-th fission product at U-238 reactor neutron 4020600200006 fission was defined as 4020600200007 Yi(U238)=Yi(U235thrm)*(Y(238,La)*Ai(238)*A(235,La))/ 4020600200008 (Y(235,La)*Ai(235)*A(238,La)) , where 4020600200009 Yi(U235thrm) - yield of i-th product at U-235 thermal 4020600200010 neutron fission; 4020600200011 Y(238,La),Y(235,La) - yields of La-140 at U-238 and 4020600200012 U-235 fission; 4020600200013 Ai(238), Ai(235) - photopeaks areas for i-th product in4020600200014 gamma-spectra of U-238 ( depleted sample) 4020600200015 and U-235 (enriched sample); 4020600200016 A(238,La), A(235,La) - La-140 activities in depleted 4020600200017 and enriched sample. 4020600200018 ERR-ANALYS (ERR-S) Error of measurement 4020600200019 (ERR-1) Error due to uncertainty of nuclear data 4020600200020 (MONIT-ERR) Monitor value uncertainty; is included in 4020600200021 ERR-T (and MISC ) if given in MONIT-REF . 4020600200022 (ERR-T) Total error 4020600200023 MISC-COL (MISC) Absolute total error. 4020600200024 HISTORY (19911125U) Error headings changed 4020600200025 (20151130A)M.M. Data were corrected as given in Tables.4020600200026 MONITOR, its values, MONIT-REF, ANALYSIS were added. 4020600200027 DATA-ERR -> MISC according to a comment of 4020600200028 N.Otsuka (NDS,IAEA). 4020600200029 STATUS (TABLE) Table 1 of SJA,36,75,1974 4020600200030 Table I of C,73KIEV,3,315,1973 4020600200031 (DEP,40206003) Ratio of yields U238/U235 . 4020600200032 ENDBIB 30 0 4020600200033 COMMON 2 3 4020600200034 EN-NRM EN-DUMMY 4020600200035 EV MEV 4020600200036 0.0253 1. 4020600200037 ENDCOMMON 3 0 4020600200038 DATA 10 10 4020600200039 ELEMENT MASS DATA ERR-T ERR-1 ERR-S 4020600200040 MISC MONIT MONIT-ERR DECAY-FLAG 4020600200041 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 4020600200042 PC/FIS PC/FIS PER-CENT NO-DIM 4020600200043 41. 95. 5.46 3.0 4020600200044 0.19 6.52 1. 4020600200045 41. 97. 6.06 2.4 4020600200046 0.19 6.05 2. 4020600200047 44. 103. 5.94 5.5 5.4 1.2 4020600200048 0.33 2.85 5. 3. 4020600200049 53. 131. 2.91 5.2 2.6 4.5 4020600200050 0.15 2.79 1.8 4. 4020600200051 53. 132. 4.75 1.2 4020600200052 0.11 4.16 5. 4020600200053 53. 133. 6.92 3.3 2.5 2.1 4020600200054 0.23 6.75 1.6 6. 4020600200055 58. 141. 4.90 1.4 4020600200056 0.12 5.84 7. 4020600200057 58. 143. 4.84 2.9 2.6 1.2 4020600200058 0.14 5.93 1.8 8. 4020600200059 58. 144. 4.34 1.6 4020600200060 0.11 5.41 9. 4020600200061 60. 147. 3.14 4.2 2.5 3.3 4020600200062 0.13 2.23 1.6 10. 4020600200063 ENDDATA 24 0 4020600200064 ENDSUBENT 63 0 4020600299999 SUBENT 40206003 20151130 41734020600300001 BIB 7 24 4020600300002 REACTION ((92-U-238(N,F)ELEM/MASS,CUM,FY)// 4020600300003 (92-U-235(N,F)ELEM/MASS,CUM,FY)) 4020600300004 Ratio of yield at U-238 reactor neutrons fission to 4020600300005 yield at U-235 thermal neutrons fission. 4020600300006 ANALYSIS Ratio Yi(U238)/Yi(U235thrm) was determined using value 4020600300007 Y(235,La)/Y(238,La)=1.05+-0.02 in three sets of 4020600300008 measurements, each of 5 measurements for short-lived an4020600300009 10 for ling-lived fission products. 4020600300010 Y(238,La),Y(235,La) - yields of La-140 at U-238 and 4020600300011 U-235 fission. 4020600300012 ASSUMED (ASSUM1,92-U-238(N,F)57-LA-140,IND,FY) 6.03+-0.07 %/fis4020600300013 Weighted average of 7 works : 6.15, 6.0, 5.96, 6.03, 4020600300014 6.34, 6.01, 5.7 %/fis. 4020600300015 (ASSUM2,92-U-235(N,F)57-LA-140,IND,FY) 6.34+-0.10 %/fis4020600300016 for thermal neutrons . 4020600300017 ERR-ANALYS (ERR-S) Error of measurement 4020600300018 (ERR-1) Error due to uncertainty of nuclear data 4020600300019 (ERR-T) Total error (relative) 4020600300020 MISC-COL (MISC) Absolute total uncertainty. 4020600300021 STATUS (TABLE) Table 2 of SJA,36,75,1974 4020600300022 = Table II of C,73KIEV,3,315,1973 4020600300023 HISTORY (19911125U) Data-units corrected 4020600300024 (20151130A) M.M. ERR-1 was moved in COMMON, 4020600300025 DATA-ERR,ASSUMED were added. 4020600300026 ENDBIB 24 0 4020600300027 COMMON 7 6 4020600300028 EN-DUM-NM EN-DUM-DN ERR-1 ASSUM1 ASSUM1-ERR ASSUM2 4020600300029 ASSUM2-ERR 4020600300030 MEV EV PER-CENT PC/FIS PC/FIS PC/FIS 4020600300031 PC/FIS 4020600300032 1. 0.0253 1.9 6.03 0.07 6.34 4020600300033 0.10 4020600300034 ENDCOMMON 6 0 4020600300035 DATA 7 10 4020600300036 ELEMENT MASS DATA ERR-T ERR-S MISC 4020600300037 DECAY-FLAG 4020600300038 NO-DIM NO-DIM NO-DIM PER-CENT PER-CENT NO-DIM 4020600300039 NO-DIM 4020600300040 41. 95. 0.838 3.5 3.0 0.029 4020600300041 1. 4020600300042 41. 97. 1.002 3.1 2.4 0.031 4020600300043 2. 4020600300044 44. 103. 2.085 2.3 1.2 0.048 4020600300045 3. 4020600300046 53. 131. 1.042 4.9 4.5 0.051 4020600300047 4. 4020600300048 53. 132. 1.142 2.3 1.2 0.026 4020600300049 5. 4020600300050 53. 133. 1.025 2.8 2.1 0.029 4020600300051 6. 4020600300052 58. 141. 0.839 2.4 1.4 0.020 4020600300053 7. 4020600300054 58. 143. 0.816 2.3 1.2 0.019 4020600300055 8. 4020600300056 58. 144. 0.802 2.5 1.6 0.020 4020600300057 9. 4020600300058 60. 147. 1.406 3.8 3.3 0.053 4020600300059 10. 4020600300060 ENDDATA 24 0 4020600300061 ENDSUBENT 60 0 4020600399999 ENDENTRY 3 0 4020699999999