ENTRY 21707 20181002 22732170700000001 SUBENT 21707001 20181002 22732170700100001 BIB 16 81 2170700100002 TITLE Fission product yields of 233-U, 235-U, 238-U and 2170700100003 239-Pu in fields of thermal neutrons, fission neutrons 2170700100004 and 14.7-MeV neutrons. 2170700100005 AUTHOR (J.Laurec, A.Adam, T.de Bruyne, E.Bauge, T.Granier, 2170700100006 J.Aupiais,O.Bersillon, G.Le Petit, N.Authier, P.Casoli)2170700100007 INSTITUTE (2FR BRC) Service Radiochimie Et Phenemologie. 2170700100008 REFERENCE (J,NDS,111,2965,2010) Re-analyzed data. 2170700100009 (C,2011BRETTO,,463,2011) - same data presented 2170700100010 (R,CEA-R-5147,1981) Main reference. (In French). 2170700100011 Determination of the fission yields of U-233, U-235, 2170700100012 U-238, Pu-239 induced by a spectra of fission 2170700100013 neutrons and neutrons of 14.7 MeV. 2170700100014 (Determination des rendements de fissions induites 2170700100015 par un spectre de neutrons de fission et des neutrons 2170700100016 de 14.7 MeV dans U-233,U-235,U-238,Pu-239). 2170700100017 (W,GOUTIERE,19810106) Private communication of 2170700100018 Goutiere, with experimental details and data. 2170700100019 REL-REF (O,21708001,J.Laurec+,J,NDS,111,2965,2010) - Data from 2170700100020 experiment done with accelerator at En=14.7 MeV 2170700100021 FACILITY (REAC,2FR BRC) Critical assemblies Prospero and 2170700100022 Caliban, C.E.Valduc. 2170700100023 INC-SOURCE (REAC) Critical assembly. 2170700100024 INC-SPECT .Fission neutron spectrum from critical 2170700100025 assembly. 2170700100026 Caliban: mean neutron energy in the cavity is 1.35 MeV.2170700100027 Prospero-U: mean neutron energy within the cavity is 2170700100028 about 1.25 MeV, outside the assembly - about 0.75 MeV; 2170700100029 neutron flux was 10**11 neutron/cm2/s within the cavity2170700100030 and 10**10 n/cm2/s outside the assembly . 2170700100031 SAMPLE Thin deposits ( made by electroplating) - for fission 2170700100032 chambers; 2170700100033 thicker ones (made by electrospraying) - for fission 2170700100034 products analysis. 2170700100035 METHOD (CHSEP) Radiochemical method, direct measurement of 2170700100036 the number of fissions and of the fission product 2170700100037 activities.Used for low-activity Ce-144,Eu-155,Eu-156.2170700100038 DETECTOR (FISCH) Plane fission chamber for the measurements 2170700100039 of the numbers of fissions. 2170700100040 (GELI ) Calibrated Ge-Li spectrometers. 2170700100041 CORRECTION .For the difference of the neutron flux between the 2170700100042 fission chamber and the target deposits. 2170700100043 For contribution from fissile materials. 2170700100044 ERR-ANALYS (ERR-1) Measurement uncertainty (1-sigma) which was 2170700100045 derived from MISC by compiler. Measurement uncertainty2170700100046 doesn't include nuclear data uncertainty 2170700100047 MISC-COL (MISC) Measurement uncertainty (2sigma) presented by 2170700100048 the author used to define ERR-1. 2170700100049 The measurement uncertainty is the quadrature sum of 2170700100050 the following uncertainties (2sigma): 2170700100051 * Statistical uncertainty of photopeak area (0.3-6.%) 2170700100052 * Statistical error of samples mass ratio (1.-2.%) 2170700100053 * Statistical uncertainty of measurement of 2170700100054 number of fissions (0.5%) 2170700100055 * Statistical uncertainty of neutron flux 2170700100056 readjustment (0.-1.5%) 2170700100057 * Systematical uncertainty of gamma detection 2170700100058 efficiency (2%) 2170700100059 * Systematical uncertainty of samples mass ratio(0.8%)2170700100060 COMMENT .Target and chamber deposits masses are determined by 2170700100061 alpha and mass spectrometry. 2170700100062 From Dr E.Bauge: On p.35 of CEA-R report, the 2170700100063 uncertainties are quoted as 2-sigma (we checked that 2170700100064 with the original authors before publishing table III 2170700100065 of the NDS, as well as against internal CEA reports 2170700100066 where more details are given (ref. 3,4,5 in the NDS)). 2170700100067 HISTORY (19810114C) G.C. 2170700100068 (19840806A) Main reference received. 2170700100069 Data updated and U-233 data added. 2170700100070 (19850821U) HH 2170700100071 (20111113A) Upper -> lower case correction. 2170700100072 Dates were corrected for 4-digits year. 2170700100073 Old data were superseded by newer re-analyzed data 2170700100074 of Nucl.Data Sheets,111(2010)2965 2170700100075 (20171106A) SD: New ref. was added. Small corrections 2170700100076 in Subents 002-004 (HISTORY code update). 2170700100077 Comment for the ref. 2001BRETTO corrected according to 2170700100078 remark from Dr Granier. REL-REF added. 2170700100079 (20181001A) SD: Comment from Dr E.Bauge was added. 2170700100080 ERR-ANALYS was updated in all Subents. MISC-COL moved 2170700100081 to Subent 001. Refs on progress reports deleted (no 2170700100082 useful information for EXFOR). 2170700100083 ENDBIB 81 0 2170700100084 NOCOMMON 0 0 2170700100085 ENDSUBENT 84 0 2170700199999 SUBENT 21707002 20181002 22732170700200001 BIB 4 15 2170700200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700200003 SAMPLE .U(3)-O(8) targets on aluminum or titanium foils. 2170700200004 Diameter 14 mm, enrichment 99.9% U-235. 2170700200005 Isotopic ratios U-234/U-235 7.0*10**-6, 2170700200006 U-238/U-235 9.0*10**-6. 2170700200007 STATUS (TABLE) Tbl. IV from R,CEA-R-5147,1981 2170700200008 (SPSDD,21707005) Superseded by re-analyzed data. 2170700200009 HISTORY (19810114C) G.C. 2170700200010 (19840806A) Data updated. 2170700200011 (19850821U)HH 2170700200012 (20111113A) STATUS 'SPSDD' was added. 2170700200013 (20171106A) SD: HISTORY (2011) record was added. 2170700200014 Meaningless zeros were deleted from the data. 2170700200015 (20181002U) SD: DATA-ERR -> MISC. ERR-ANALYS deleted 2170700200016 (information moved to Subent 001). ERR-1 was added. 2170700200017 ENDBIB 15 0 2170700200018 COMMON 1 3 2170700200019 EN-DUMMY 2170700200020 MEV 2170700200021 1.5 2170700200022 ENDCOMMON 3 0 2170700200023 DATA 5 14 2170700200024 ELEMENT MASS DATA ERR-1 MISC 2170700200025 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170700200026 40. 95. 6.29 2.0 4.0 2170700200027 40. 97. 5.88 1.65 3.3 2170700200028 42. 99. 6.23 1.45 2.9 2170700200029 44. 103. 3.25 1.8 3.6 2170700200030 44. 106. 0.5552 5.0 10. 2170700200031 52. 132. 4.76 1.5 3.0 2170700200032 53. 131. 3.32 1.05 3.1 2170700200033 53. 133. 5.90 2.7 5.4 2170700200034 55. 137. 6.14 4.25 8.5 2170700200035 56. 140. 5.96 1.95 3.9 2170700200036 58. 141. 5.83 1.95 3.9 2170700200037 58. 143. 5.41 1.6 3.2 2170700200038 58. 144. 5.07 2.25 4.5 2170700200039 60. 147. 2.27 2.25 4.5 2170700200040 ENDDATA 16 0 2170700200041 ENDSUBENT 40 0 2170700299999 SUBENT 21707003 20181002 22732170700300001 BIB 4 16 2170700300002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700300003 SAMPLE .Pu-O(2) Targets on aluminum or titanium foils. 2170700300004 Target diameter 14 mm, enrichment in Pu-239 better 2170700300005 than 98.% 2170700300006 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170700300007 Pu-241/Pu-239 3.7*10**-4. 2170700300008 STATUS (TABLE) Tbl. V from R,CEA-R-5147,1981 2170700300009 (SPSDD,21707007) Superseded by re-analyzed data. 2170700300010 HISTORY (19810114C) G.C. 2170700300011 (19840806A) Data updated. 2170700300012 (19850821U)HH 2170700300013 (20111113A) STATUS 'SPSDD' was added. 2170700300014 (20171106A) SD: HISTORY (2011) record was added. 2170700300015 Meaningless zeros were deleted from the data. 2170700300016 (20181002U) SD: DATA-ERR -> MISC. ERR-ANALYS deleted 2170700300017 (information moved to Subent 001). ERR-1 was added. 2170700300018 ENDBIB 16 0 2170700300019 COMMON 1 3 2170700300020 EN-DUMMY 2170700300021 MEV 2170700300022 1.5 2170700300023 ENDCOMMON 3 0 2170700300024 DATA 5 15 2170700300025 ELEMENT MASS DATA ERR-1 MISC 2170700300026 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170700300027 40. 95. 4.48 1.75 3.5 2170700300028 40. 97. 5.02 1.85 3.7 2170700300029 42. 99. 5.94 1.5 3.0 2170700300030 44. 103. 6.58 1.6 3.2 2170700300031 44. 106. 3.96 3.25 6.5 2170700300032 45. 105. 5.22 2.45 4.9 2170700300033 52. 132. 4.87 1.65 3.3 2170700300034 53. 131. 3.63 2.35 4.7 2170700300035 53. 133. 5.92 3.0 6.0 2170700300036 55. 136. 0.111 3.25 6.5 2170700300037 56. 140. 4.98 2.25 4.5 2170700300038 58. 141. 4.84 2.15 4.3 2170700300039 58. 143. 4.08 1.8 3.6 2170700300040 58. 144. 3.58 2.0 4.0 2170700300041 60. 147. 2. 2.0 4.0 2170700300042 ENDDATA 17 0 2170700300043 ENDSUBENT 42 0 2170700399999 SUBENT 21707004 20181002 22732170700400001 BIB 4 14 2170700400002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700400003 SAMPLE .U(3)-O(8) Targets on aluminum or titanium foils. 2170700400004 Diameter 14 mm, enrichment 99.9% U-233. 2170700400005 Isotopic ratios U-234/U-233 4.2*10**-3, 2170700400006 U-238/U-233 1.8*10**-2, U-232/U-233 2.3*10**-6. 2170700400007 STATUS (TABLE) Tbl. III from R,CEA-R-5147,1981 2170700400008 (SPSDD,21707009) Superseded by re-analyzed data. 2170700400009 HISTORY (19840806C) BN. SUBENTRY Added. 2170700400010 (19850821U)HH 2170700400011 (20111113A) STATUS 'SPSDD' was added. 2170700400012 (20171106A) SD: HISTORY (2011) record was added. 2170700400013 Meaningless zeros were deleted from the data. 2170700400014 (20181002U) SD: DATA-ERR -> MISC. ERR-ANALYS deleted 2170700400015 (information moved to Subent 001). ERR-1 was added. 2170700400016 ENDBIB 14 0 2170700400017 COMMON 1 3 2170700400018 EN-DUMMY 2170700400019 MEV 2170700400020 1.5 2170700400021 ENDCOMMON 3 0 2170700400022 DATA 5 15 2170700400023 ELEMENT MASS DATA ERR-1 MISC 2170700400024 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170700400025 40. 95. 6.40 2.3 4.6 2170700400026 40. 97. 5.51 1.8 3.6 2170700400027 42. 99. 4.91 1.75 3.5 2170700400028 44. 103. 1.68 2.45 4.9 2170700400029 52. 132. 4.62 1.75 3.5 2170700400030 53. 131. 3.81 1.8 3.6 2170700400031 53. 133. 5.54 1.85 3.7 2170700400032 54. 135. 5.40 4.0 8.0 2170700400033 55. 136. 0.116 3.65 7.3 2170700400034 55. 137. 6.20 6.0 12. 2170700400035 56. 140. 6.08 1.85 3.7 2170700400036 58. 141. 6.29 1.8 3.6 2170700400037 58. 143. 5.38 1.85 3.7 2170700400038 58. 144. 4.52 2.4 4.8 2170700400039 60. 147. 1.76 2.45 4.9 2170700400040 ENDDATA 17 0 2170700400041 ENDSUBENT 40 0 2170700499999 SUBENT 21707005 20181002 22732170700500001 BIB 7 55 2170700500002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700500003 SAMPLE .U(3)-O(8) targets on aluminum or titanium foils. 2170700500004 Diameter 14 mm, enrichment 99.9% U-235. 2170700500005 Isotopic ratios U-234/U-235 7.0*10**-6, 2170700500006 U-238/U-235 9.0*10**-6. 2170700500007 ANALYSIS Final value for each fission product is the combination2170700500008 of these different measurements through weighted 2170700500009 averages, the weight being defined as the inverse of 2170700500010 the square of the statistical uncertainty associated 2170700500011 with each individual measurement. 2170700500012 Old yields data were updated as: 2170700500013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170700500014 w1, w2 - normalized weights corresponding to each gamma2170700500015 line: 2170700500016 95Zr 724 keV 50%, 757 keV 50%; 2170700500017 97Zr 658 keV 50%, 743 keV 50%; 2170700500018 140Ba 163 keV 50%, 537 keV 50%; 2170700500019 147Nd 91 keV 50%, 531 keV 50%; 2170700500020 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170700500021 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170700500022 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170700500023 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170700500024 (42-MO-99,2.747D,DG,140.5,0.8906) 2170700500025 89.06+-0.24 ; 2.747+-4E-4 . 2170700500026 (44-RU-103,39.26D,DG,497.1,0.910) 2170700500027 91.0+-1.2 ; 39.26+-0.02 . 2170700500028 (44-RU-106,371.8D,DG,621.9,0.0993) 2170700500029 9.93+-0.23 ; 371.8+-1.8. 2170700500030 (53-I-131,8.025D,DG,364.5,0.815) 2170700500031 81.5+-0.8 ; 8.025+-0.001 . 2170700500032 (53-I-133-G,0.867D,DG,529.5,0.870) 2170700500033 87.0+-3.0 ; 0.867+-0.004 . 2170700500034 (52-TE-132,3.204D,DG,228.2,0.88) 2170700500035 88+-3 ; 3.204+-0.013 . 2170700500036 (55-CS-137,10979.2D,DG,661.6,0.8510) 2170700500037 85.10+-0.2 ; 10979.2+-32.85 . 2170700500038 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170700500039 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170700500040 (58-CE-141,32.508D,DG,145.4,0.4829) 2170700500041 48.29+-0.20 ; 32.508+-0.013 . 2170700500042 (58-CE-143,1.376D,DG,293.3,0.428) 2170700500043 42.8+-0.4 ; 1.376+-0.002 . 2170700500044 (58-CE-144,284.91D,DG,133.5,0.1109) 2170700500045 11.09+-0.19 ; 284.91+-0.05 . 2170700500046 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170700500047 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170700500048 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170700500049 combination of ERR-1 (see Subent 001) and nuclear data 2170700500050 uncertainties 2170700500051 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170700500052 (gamma intensity and half-life). 2170700500053 STATUS (TABLE) Table X of Nucl.Data Sheets,111(2010)2965. 2170700500054 (DEP,21707002) Subent 002 data were re-analyzed data. 2170700500055 HISTORY (20111113C) M.M. 2170700500056 (20181002U) SD: ERR-ANALYS was updated. 2170700500057 ENDBIB 55 0 2170700500058 COMMON 1 3 2170700500059 EN-MEAN 2170700500060 MEV 2170700500061 1.25 2170700500062 ENDCOMMON 3 0 2170700500063 DATA 7 14 2170700500064 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170700500065 MISC 2170700500066 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170700500067 PER-CENT 2170700500068 40. 95. 6.32 2.1 0.3 2.1 2170700500069 4.2 2170700500070 40. 97. 5.82 1.9 0.1 1.9 2170700500071 3.8 2170700500072 42. 99. 6.27 1.7 0.3 1.7 2170700500073 3.4 2170700500074 44. 103. 3.18 2.05 1.3 2.4 2170700500075 4.1 2170700500076 44. 106. 0.56 5.25 2.3 5.7 2170700500077 10.5 2170700500078 52. 132. 4.76 1.75 3.4 3.9 2170700500079 3.5 2170700500080 53. 131. 3.34 1.8 1.0 2.1 2170700500081 3.6 2170700500082 53. 133. 5.90 1.45 3.3 4.5 2170700500083 2.9 2170700500084 55. 137. 6.11 4.5 0.2 4.5 2170700500085 9.0 2170700500086 56. 140. 5.84 2.2 0.9 2.4 2170700500087 4.4 2170700500088 58. 141. 5.85 2.2 0.4 2.2 2170700500089 4.4 2170700500090 58. 143. 5.31 1.85 0.9 2.1 2170700500091 3.7 2170700500092 58. 144. 4.97 2.5 1.7 3.0 2170700500093 5.0 2170700500094 60. 147. 2.04 2.5 4.2 4.9 2170700500095 5.0 2170700500096 ENDDATA 32 0 2170700500097 ENDSUBENT 96 0 2170700599999 SUBENT 21707006 20181002 22732170700600001 BIB 7 30 2170700600002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700600003 SAMPLE .U(3)-O(8) targets on aluminum or titanium foils. 2170700600004 Diameter 14 mm, enrichment 99.9% U-235. 2170700600005 Isotopic ratios U-234/U-235 7.0*10**-6, 2170700600006 U-238/U-235 9.0*10**-6. 2170700600007 ANALYSIS Final value for each fission product is the combination2170700600008 of these different measurements through weighted 2170700600009 averages, the weight being defined as the inverse of 2170700600010 the square of the statistical uncertainty associated 2170700600011 with each individual measurement. 2170700600012 Old yields data were updated as: 2170700600013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170700600014 w1, w2 - normalized weights corresponding to each gamma2170700600015 line: 2170700600016 95Zr 724 keV 50%, 757 keV 50%; 2170700600017 147Nd 91 keV 50%, 531 keV 50%; 2170700600018 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170700600019 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170700600020 (58-CE-144,284.91D,DG,133.5,0.1109) 2170700600021 11.09+-0.19 ; 284.91+-0.05 . 2170700600022 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170700600023 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170700600024 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170700600025 combination of ERR-1 (see Subent 001) and nuclear data 2170700600026 uncertainties 2170700600027 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170700600028 (gamma intensity and half-life). 2170700600029 STATUS (TABLE) Table X of Nucl.Data Sheets,111(2010)2965. 2170700600030 HISTORY (20111113C) M.M. 2170700600031 (20181002U) SD: ERR-ANALYS was updated. 2170700600032 ENDBIB 30 0 2170700600033 COMMON 1 3 2170700600034 EN-MEAN 2170700600035 MEV 2170700600036 0.7 2170700600037 ENDCOMMON 3 0 2170700600038 DATA 7 3 2170700600039 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170700600040 MISC 2170700600041 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170700600042 PER-CENT 2170700600043 40. 95. 6.23 2.25 0.3 2.3 2170700600044 4.5 2170700600045 58. 144. 5.08 2.5 1.7 3.0 2170700600046 5.0 2170700600047 60. 147. 2.12 2.5 4.2 4.9 2170700600048 5.0 2170700600049 ENDDATA 10 0 2170700600050 ENDSUBENT 49 0 2170700699999 SUBENT 21707007 20181002 22732170700700001 BIB 7 55 2170700700002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700700003 SAMPLE .Pu-O(2) Targets on aluminum or titanium foils. 2170700700004 Target diameter 14 mm, enrichment in Pu-239 better 2170700700005 than 98.%. 2170700700006 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170700700007 Pu-241/Pu-239 3.7*10**-4. 2170700700008 ANALYSIS Final value for each fission product is the combination2170700700009 of these different measurements through weighted 2170700700010 averages, the weight being defined as the inverse of 2170700700011 the square of the statistical uncertainty associated 2170700700012 with each individual measurement. 2170700700013 Old yields data were updated as: 2170700700014 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170700700015 w1, w2 - normalized weights corresponding to each gamma2170700700016 line: 2170700700017 95Zr 724 keV 50%, 757 keV 50%; 2170700700018 97Zr 658 keV 50%, 743 keV 50%; 2170700700019 136Cs 818 keV 60%, 1048 keV 40%; 2170700700020 140Ba 163 keV 50%, 537 keV 50%; 2170700700021 147Nd 91 keV 50%, 531 keV 50% . 2170700700022 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170700700023 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170700700024 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170700700025 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170700700026 (42-MO-99,2.747D,DG,140.5,0.8906) 2170700700027 89.06+-0.24 ; 2.747+-4E-4 . 2170700700028 (44-RU-103,39.26D,DG,497.1,0.910) 2170700700029 91.0+-1.2 ; 39.26+-0.02 . 2170700700030 (45-RH-105-G,1.473D,DG,318.9,0.191) 2170700700031 19.1+-0.6 ; 1.473+-0.002. 2170700700032 (53-I-131,8.025D,DG,364.5,0.815) 2170700700033 81.5+-0.8 ; 8.025+-0.001 . 2170700700034 (53-I-133-G,0.867D,DG,529.5,0.870) 2170700700035 87.0+-3.0 ; 0.867+-0.004 . 2170700700036 (52-TE-132,3.204D,DG,228.2,0.88) 2170700700037 88+-3 ; 3.204+-0.013 . 2170700700038 (55-CS-136-G,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170700700039 13.04+-0.03 ; 80.+-3. . 2170700700040 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170700700041 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170700700042 (58-CE-141,32.508D,DG,145.4,0.4829) 2170700700043 48.29+-0.20 ; 32.508+-0.013 . 2170700700044 (58-CE-143,1.376D,DG,293.3,0.428) 2170700700045 42.8+-0.4 ; 1.376+-0.002 . 2170700700046 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170700700047 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170700700048 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170700700049 combination of ERR-1 (see Subent 001) and nuclear data 2170700700050 uncertainties 2170700700051 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170700700052 (gamma intensity and half-life). 2170700700053 STATUS (TABLE) Table XI of Nucl.Data Sheets,111(2010)2965. 2170700700054 (DEP,21707003) Subent 003 data were re-analyzed data. 2170700700055 HISTORY (20111113C) M.M. 2170700700056 (20181002U) SD: ERR-ANALYS was updated. 2170700700057 ENDBIB 55 0 2170700700058 COMMON 1 3 2170700700059 EN-MEAN 2170700700060 MEV 2170700700061 1.25 2170700700062 ENDCOMMON 3 0 2170700700063 DATA 7 13 2170700700064 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170700700065 MISC 2170700700066 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170700700067 PER-CENT 2170700700068 40. 95. 4.47 2.05 0.3 2.1 2170700700069 4.1 2170700700070 40. 97. 4.97 2.1 0.1 2.1 2170700700071 4.2 2170700700072 42. 99. 5.98 1.75 0.3 1.8 2170700700073 3.5 2170700700074 44. 103. 6.45 1.85 1.3 2.3 2170700700075 3.7 2170700700076 45. 105. 5.16 2.7 3.1 4.1 2170700700077 5.4 2170700700078 52. 132. 4.87 1.9 3.4 3.9 2170700700079 3.8 2170700700080 53. 131. 3.65 2.6 1.0 2.8 2170700700081 5.2 2170700700082 53. 133. 5.92 3.25 3.3 4.7 2170700700083 6.5 2170700700084 55. 136. 0.11 3.5 1.5 3.8 2170700700085 7.0 2170700700086 56. 140. 4.88 2.5 0.9 2.6 2170700700087 5.0 2170700700088 58. 141. 4.86 2.4 0.4 2.4 2170700700089 4.8 2170700700090 58. 143. 4.00 2.05 0.9 2.3 2170700700091 4.1 2170700700092 60. 147. 1.86 2.15 4.2 4.8 2170700700093 4.3 2170700700094 ENDDATA 30 0 2170700700095 ENDSUBENT 94 0 2170700799999 SUBENT 21707008 20181002 22732170700800001 BIB 7 33 2170700800002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700800003 SAMPLE .PU-O(2) Targets on aluminum or titanium foils. 2170700800004 Target diameter 14 mm, enrichment in Pu-239 better 2170700800005 than 98.%. 2170700800006 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170700800007 Pu-241/Pu-239 3.7*10**-4. 2170700800008 ANALYSIS Final value for each fission product is the combination2170700800009 of these different measurements through weighted 2170700800010 averages, the weight being defined as the inverse of 2170700800011 the square of the statistical uncertainty associated 2170700800012 with each individual measurement. 2170700800013 Old yields data were updated as: 2170700800014 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170700800015 w1, w2 - normalized weights corresponding to each gamma2170700800016 line: 2170700800017 95Zr 724 keV 50%, 757 keV 50%; 2170700800018 147Nd 91 keV 50%, 531 keV 50% . 2170700800019 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170700800020 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170700800021 (44-RU-106,371.8D,DG,621.9,0.0993) 2170700800022 9.93+-0.23 ; 371.8+-1.8. 2170700800023 (58-CE-144,284.91D,DG,133.5,0.1109) 2170700800024 11.09+-0.19 ; 284.91+-0.05 . 2170700800025 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170700800026 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170700800027 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170700800028 combination of ERR-1 (see Subent 001) and nuclear data 2170700800029 uncertainties 2170700800030 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170700800031 (gamma intensity and half-life). 2170700800032 STATUS (TABLE) Table XI of Nucl.Data Sheets,111(2010)2965. 2170700800033 HISTORY (20111113C) M.M. 2170700800034 (20181002U) SD: ERR-ANALYS was updated. 2170700800035 ENDBIB 33 0 2170700800036 COMMON 1 3 2170700800037 EN-MEAN 2170700800038 MEV 2170700800039 0.8 2170700800040 ENDCOMMON 3 0 2170700800041 DATA 7 4 2170700800042 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170700800043 MISC 2170700800044 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170700800045 PER-CENT 2170700800046 40. 95. 4.44 2.0 0.3 2.0 2170700800047 4.0 2170700800048 44. 106. 3.99 3.5 2.3 4.2 2170700800049 7.0 2170700800050 58. 144. 3.59 2.25 1.7 2.8 2170700800051 4.5 2170700800052 60. 147. 1.86 2.25 4.2 4.7 2170700800053 4.5 2170700800054 ENDDATA 12 0 2170700800055 ENDSUBENT 54 0 2170700899999 SUBENT 21707009 20181002 22732170700900001 BIB 8 61 2170700900002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY,,FIS) 2170700900003 SAMPLE .U(3)-O(8) Targets on aluminum or titanium foils. 2170700900004 Diameter 14 mm, enrichment 99.9% U-233. 2170700900005 Isotopic ratios U-234/U-233 4.2*10**-3, 2170700900006 U-238/U-233 1.8*10**-2, U-232/U-233 2.3*10**-6. 2170700900007 ANALYSIS Final value for each fission product is the combination2170700900008 of these different measurements through weighted 2170700900009 averages, the weight being defined as the inverse of 2170700900010 the square of the statistical uncertainty associated 2170700900011 with each individual measurement. 2170700900012 Old yields data were updated as: 2170700900013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170700900014 w1, w2 - normalized weights corresponding to each gamma2170700900015 line: 2170700900016 95Zr 724 keV 50%, 757 keV 50%; 2170700900017 97Zr 658 keV 50%, 743 keV 50%; 2170700900018 136Cs 818 keV 60%, 1048 keV 40%; 2170700900019 140Ba 163 keV 50%, 537 keV 50%; 2170700900020 147Nd 91 keV 50%, 531 keV 50%; 2170700900021 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170700900022 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170700900023 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170700900024 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170700900025 (42-MO-99,2.747D,DG,140.5,0.8906) 2170700900026 89.06+-0.24 ; 2.747+-4E-4 . 2170700900027 (44-RU-103,39.26D,DG,497.1,0.910) 2170700900028 91.0+-1.2 ; 39.26+-0.02 . 2170700900029 (53-I-131,8.025D,DG,364.5,0.815) 2170700900030 81.5+-0.8 ; 8.025+-0.001 . 2170700900031 (53-I-133-G,0.867D,DG,529.5,0.870) 2170700900032 87.0+-3.0 ; 0.867+-0.004 . 2170700900033 (52-TE-132,3.204D,DG,228.2,0.88) 2170700900034 88+-3 ; 3.204+-0.013 . 2170700900035 (54-XE-135-G,0.381D,DG,249.8,0.90) 2170700900036 90+-3 ; 0.381+-0.001 . 2170700900037 (55-CS-136-G,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170700900038 13.04+-0.03 ; 80.+-3. . 2170700900039 (55-CS-137,10979.2D,DG,661.6,0.8510) 2170700900040 85.10+-0.2 ; 10979.2+-32.85 . 2170700900041 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170700900042 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170700900043 (58-CE-141,32.508D,DG,145.4,0.4829) 2170700900044 48.29+-0.20 ; 32.508+-0.013 . 2170700900045 (58-CE-143,1.376D,DG,293.3,0.428) 2170700900046 42.8+-0.4 ; 1.376+-0.002 . 2170700900047 (58-CE-144,284.91D,DG,133.5,0.1109) 2170700900048 11.09+-0.19 ; 284.91+-0.05 . 2170700900049 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170700900050 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170700900051 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170700900052 combination of ERR-1 (see Subent 001) and nuclear data 2170700900053 uncertainties 2170700900054 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170700900055 (gamma intensity and half-life). 2170700900056 COMMENT T.Granier (2018-09-10): 233U(n,f)133I yield in the 2170700900057 2010 article (5.54%) must be used though another 2170700900058 value (5.45%) is printed in the 2011 article. 2170700900059 STATUS (TABLE) Table VIII of Nucl.Data Sheets,111(2010)2965. 2170700900060 (DEP,21707004) Subent 004 data were re-analyzed data. 2170700900061 HISTORY (20111113C) M.M. 2170700900062 (20181002U) SD: ERR-ANALYS was updated. 2170700900063 ENDBIB 61 0 2170700900064 COMMON 1 3 2170700900065 EN-MEAN 2170700900066 MEV 2170700900067 0.77 2170700900068 ENDCOMMON 3 0 2170700900069 DATA 7 15 2170700900070 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170700900071 MISC 2170700900072 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170700900073 PER-CENT 2170700900074 40. 95. 6.34 2.55 0.3 2.6 2170700900075 5.1 2170700900076 40. 97. 5.46 2.05 0.1 2.1 2170700900077 4.1 2170700900078 42. 99. 4.94 2.0 0.3 2.0 2170700900079 4.0 2170700900080 44. 103. 1.65 2.7 1.3 3.0 2170700900081 5.4 2170700900082 52. 132. 4.62 2.0 3.4 4.0 2170700900083 4.0 2170700900084 53. 131. 3.84 2.05 1.0 2.3 2170700900085 4.1 2170700900086 53. 133. 5.54 2.1 3.3 3.9 2170700900087 4.2 2170700900088 54. 135. 5.44 4.25 3.3 4.2 2170700900089 8.5 2170700900090 55. 136. 0.11 3.9 1.5 4.2 2170700900091 7.8 2170700900092 55. 137. 6.17 6.25 0.2 6.3 2170700900093 12.5 2170700900094 56. 140. 5.96 2.1 0.9 2.3 2170700900095 4.2 2170700900096 58. 141. 6.31 2.05 0.4 2.1 2170700900097 4.1 2170700900098 58. 143. 5.28 2.1 0.9 2.3 2170700900099 4.2 2170700900100 58. 144. 4.53 2.65 1.7 3.2 2170700900101 5.3 2170700900102 60. 147. 1.64 2.7 4.2 5.0 2170700900103 5.4 2170700900104 ENDDATA 34 0 2170700900105 ENDSUBENT 104 0 2170700999999 SUBENT 21707010 20181002 22732170701000001 BIB 7 28 2170701000002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 2170701000003 SAMPLE .U(3)-O(8) targets on aluminum or titanium foils. 2170701000004 Diameter 14 mm, enrichment 99.9% U-235. 2170701000005 Isotopic ratios U-234/U-235 7.0*10**-6, 2170701000006 U-238/U-235 9.0*10**-6. 2170701000007 ANALYSIS Final value for each fission product is the combination2170701000008 of these different measurements through weighted 2170701000009 averages, the weight being defined as the inverse of 2170701000010 the square of the statistical uncertainty associated 2170701000011 with each individual measurement. 2170701000012 Old yields data were updated as: 2170701000013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170701000014 w1, w2 - normalized weights corresponding to each gamma2170701000015 line: 2170701000016 155Eu 86 keV 50%, 105 keV 50%; 2170701000017 156Eu 89 keV 90%, 646 keV 10% . 2170701000018 DECAY-DATA (63-EU-155,1734.84D,DG,86.5,0.307,DG,105.3,0.2110) 2170701000019 30.7+-0.3 ; 1734.84+-5.11 ; 21.10+-0.5 . 2170701000020 (63-EU-156,15.19D,DG,89.0,0.084,DG,646.3,0.063) 2170701000021 8.4+-1.1 ; 15.19+-0.08 ; 6.3+-0.5 . 2170701000022 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170701000023 combination of ERR-1 (see Subent 001) and nuclear data 2170701000024 uncertainties 2170701000025 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170701000026 (gamma intensity and half-life). 2170701000027 STATUS (TABLE) Table IX of Nucl.Data Sheets,111(2010)2965. 2170701000028 HISTORY (20111113C) M.M. 2170701000029 (20181002U) SD: ERR-ANALYS was updated. 2170701000030 ENDBIB 28 0 2170701000031 COMMON 1 3 2170701000032 ELEMENT 2170701000033 NO-DIM 2170701000034 63. 2170701000035 ENDCOMMON 3 0 2170701000036 DATA 7 6 2170701000037 EN-MEAN MASS DATA ERR-1 ERR-2 ERR-T 2170701000038 MISC 2170701000039 MEV NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170701000040 PER-CENT 2170701000041 0.7 155. 3.97E-2 4.25 1.3 4.4 2170701000042 8.5 2170701000043 0.7 156. 1.77E-2 4.25 11.8 12.5 2170701000044 8.5 2170701000045 0.8 155. 3.71E-2 4.25 1.3 4.4 2170701000046 8.5 2170701000047 0.8 156. 1.67E-2 4.25 11.8 12.5 2170701000048 8.5 2170701000049 1.2 155. 3.98E-2 3.75 1.3 4.0 2170701000050 7.5 2170701000051 1.2 156. 1.86E-2 3.75 11.8 12.4 2170701000052 7.5 2170701000053 ENDDATA 16 0 2170701000054 ENDSUBENT 53 0 2170701099999 ENDENTRY 10 0 2170799999999