ENTRY 21708 20181004 22732170800000001 SUBENT 21708001 20181004 22732170800100001 BIB 15 73 2170800100002 INSTITUTE (2FR BRC) Service Radiochimie Et Phenemologie. 2170800100003 REFERENCE (J,NDS,111,2965,2010) Re-analyzed data. 2170800100004 (R,CEA-R-5147,1981) Main reference. (In French). 2170800100005 Determination of the fission yields of U-233, U-235, 2170800100006 U-238, Pu-239 induced by a spectra of fission 2170800100007 neutrons and neutrons of 14.7 MeV. 2170800100008 (Determination des rendements de fissions induites 2170800100009 par un spectre de neutrons de fission et des neutrons 2170800100010 de 14.7 MeV dans U-233,U-235,U-238,Pu-239). 2170800100011 (W,GOUTIERE,19810106) Private communication of 2170800100012 G.Goutiere with the detailed description of the 2170800100013 experiment and the data. 2170800100014 AUTHOR (J.Laurec, A.Adam, T.de Bruyne, E.Bauge, T.Granier, 2170800100015 J.Aupiais,O.Bersillon, G.Le Petit, N.Authier, P.Casoli)2170800100016 TITLE Fission Product Yields of 233-U, 235-U, 238-U and 2170800100017 239-Pu in Fields of Thermal Neutrons, Fission Neutrons 2170800100018 and 14.7-MeV Neutrons. 2170800100019 FACILITY (ACCEL,2FR ITL) Lancelot electrostatic accelerator of 2170800100020 CEA-Valduc. 2170800100021 INC-SOURCE (D-T) Deuteron-tritium reaction. 2170800100022 Deuterons at a 160 KV voltage were bombarding a 2170800100023 rotating TiT water-cooled target. 2170800100024 INC-SPECT Neutron flux at 2 cm downstream from the production 2170800100025 target, on the beam axis, was on the order of 2170800100026 5*10**10 neutron/cm**2/s. 2170800100027 SAMPLE Thin deposits ( made by electroplating) - for fission 2170800100028 chambers; 2170800100029 thicker ones (made by electrospraying) - for fission 2170800100030 products analysis. 2170800100031 METHOD (CHSEP) Radiochemical method. Direct measurement of 2170800100032 the number of fissions and of the fission product 2170800100033 activities.Used for low-activity Ce-144,Eu-155,Eu-156.2170800100034 DETECTOR (FISCH) Plane fission chamber for measurement of the 2170800100035 number of fissions. 2170800100036 (GELI) Calibrated Ge-Li spectrometers. 2170800100037 CORRECTION .For the difference of the neutron flux between the 2170800100038 fission chamber and the target deposits. 2170800100039 For contribution from fissile materials. 2170800100040 ERR-ANALYS (ERR-1) Measurement uncertainty (1-sigma) which was 2170800100041 derived from MISC by compiler. Measurement uncertainty2170800100042 doesn't include nuclear data uncertainty 2170800100043 MISC-COL (MISC) Measurement uncertainty (2sigma) presented by 2170800100044 the author used to define ERR-1. 2170800100045 The measurement uncertainty is the quadrature sum of 2170800100046 the following uncertainties (2-sigma): 2170800100047 * Statistical uncertainty of photopeak area (0.3-6.%) 2170800100048 * Statistical error of samples mass ratio (1.-2.%) 2170800100049 * Statistical uncertainty of measurement of 2170800100050 number of fissions (0.5%) 2170800100051 * Statistical uncertainty of neutron flux 2170800100052 readjustment (0.-1.5%) 2170800100053 * Systematical uncertainty of gamma detection 2170800100054 efficiency (2%) 2170800100055 * Systematical uncertainty of samples mass ratio(0.8%)2170800100056 COMMENT .Target and chamber deposits masses are determined by 2170800100057 alpha and mass spectrometry. 2170800100058 .From Dr E.Bauge: On p.35 of CEA-R report, the 2170800100059 uncertainties are quoted as 2-sigma (we checked that 2170800100060 with the original authors before publishing table III 2170800100061 of the NDS, as well as against internal CEA reports 2170800100062 where more details are given (ref. 3,4,5 in the NDS)). 2170800100063 HISTORY (19810114C) G.C. 2170800100064 (19840806A) Main reference received. 2170800100065 Data updated and U-233 data added. 2170800100066 (19850821U)HH 2170800100067 (20111113A) Upper -> lower case correction. 2170800100068 Dates were corrected for 4-digits year. 2170800100069 Old data were superseded by newer re-analyzed data 2170800100070 of Nucl.Data Sheets,111(2010)2965. 2170800100071 (20181004A) SD: Comment from Dr E.Bauge was added. 2170800100072 ERR-ANALYS was updated in all Subents. MISC-COL moved 2170800100073 to Subent 001. Refs on progress reports deleted (no 2170800100074 useful information for EXFOR). 2170800100075 ENDBIB 73 0 2170800100076 COMMON 1 3 2170800100077 EN 2170800100078 MEV 2170800100079 14.7 2170800100080 ENDCOMMON 3 0 2170800100081 ENDSUBENT 80 0 2170800199999 SUBENT 21708002 20181004 22732170800200001 BIB 4 10 2170800200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 2170800200003 SAMPLE .U(3)-O(8) Targets on aluminum foils. 2170800200004 Diameter 14 mm, enrichment 99.9% U-235. 2170800200005 Isotopic ratios U-234/U-235 7.0*10**-6, 2170800200006 U-238/U-235 9.0*10**-6. 2170800200007 STATUS (TABLE) Tbl. VII from R,CEA-R-5147,1981 2170800200008 (SPSDD,21708006) Superseded by re-analyzed data. 2170800200009 HISTORY (19810114C) G.C. 2170800200010 (20181002U) SD: ERR-T -> MISC. ERR-ANALYS deleted 2170800200011 (information moved to Subent 001). ERR-1 was added. 2170800200012 ENDBIB 10 0 2170800200013 NOCOMMON 0 0 2170800200014 DATA 5 15 2170800200015 ELEMENT MASS DATA ERR-1 MISC 2170800200016 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170800200017 40. 95. 5.33 1.9 3.8 2170800200018 40. 97. 5.03 2.5 5.0 2170800200019 42. 99. 5.05 1.9 3.8 2170800200020 44. 103. 3.08 2.05 4.1 2170800200021 51. 127. 1.76 3.75 7.5 2170800200022 52. 132. 4.14 1.95 3.9 2170800200023 53. 131. 4.32 2.0 4.0 2170800200024 53. 133. 5.43 2.45 4.9 2170800200025 54. 135. 4.97 3.2 6.4 2170800200026 55. 136. 0.22 4.5 9.0 2170800200027 56. 140. 4.61 2.1 4.2 2170800200028 58. 141. 4.5 2.0 4.0 2170800200029 58. 143. 3.75 2.05 4.1 2170800200030 58. 144. 3.15 0.5 1.0 2170800200031 60. 147. 1.62 2.4 4.8 2170800200032 ENDDATA 17 0 2170800200033 ENDSUBENT 32 0 2170800299999 SUBENT 21708003 20181004 22732170800300001 BIB 4 10 2170800300002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 2170800300003 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800300004 Target diameter 14 mm, enrichment 99.9% U-238. 2170800300005 Isotopic ratios U-234/U-238 9.0E-6 ; 2170800300006 U-235/U-238 2.0E-6 ; U-236/U-238 5.4E-6. 2170800300007 STATUS (TABLE) Tbl. VIII from R,CEA-R-5147,1981 2170800300008 (SPSDD,21708007) Superseded by re-analyzed data. 2170800300009 HISTORY (19810114C) G.C. 2170800300010 (20181002U) SD: ERR-T -> MISC. ERR-ANALYS deleted 2170800300011 (information moved to Subent 001). ERR-1 was added. 2170800300012 ENDBIB 10 0 2170800300013 NOCOMMON 0 0 2170800300014 DATA 5 15 2170800300015 ELEMENT MASS DATA ERR-1 MISC 2170800300016 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170800300017 40. 95. 4.97 2.1 4.2 2170800300018 40. 97. 5.23 2.4 4.8 2170800300019 42. 99. 5.75 1.95 3.9 2170800300020 44. 103. 4.74 2.0 4.0 2170800300021 45. 105. 3.40 3.0 6.0 2170800300022 51. 127. 1.38 2.6 5.2 2170800300023 52. 132. 4.72 1.95 3.9 2170800300024 53. 131. 4.05 2.15 4.3 2170800300025 53. 133. 5.50 3.0 6.0 2170800300026 54. 135. 5.70 2.5 5.0 2170800300027 56. 140. 4.65 2.1 4.2 2170800300028 58. 141. 4.44 2.0 4.0 2170800300029 58. 143. 3.94 2.25 4.5 2170800300030 58. 144. 3.72 3.5 7.0 2170800300031 60. 147. 2.08 2.35 4.7 2170800300032 ENDDATA 17 0 2170800300033 ENDSUBENT 32 0 2170800399999 SUBENT 21708004 20181004 22732170800400001 BIB 4 11 2170800400002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 2170800400003 SAMPLE .PU-O(2) Targets on aluminum foils. 2170800400004 Target diameter 14 mm, enrichment in Pu-239 2170800400005 better than 98.%. 2170800400006 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170800400007 Pu-241/Pu-239 3.7*10**-4. 2170800400008 STATUS (TABLE) Data taken from R,CEA-R-5147,1981 2170800400009 (SPSDD,21708008) Superseded by re-analyzed data. 2170800400010 HISTORY (19810114C) G.C. 2170800400011 (20181002U) SD: ERR-T -> MISC. ERR-ANALYS deleted 2170800400012 (information moved to Subent 001). ERR-1 was added. 2170800400013 ENDBIB 11 0 2170800400014 NOCOMMON 0 0 2170800400015 DATA 5 15 2170800400016 ELEMENT MASS DATA ERR-1 MISC 2170800400017 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170800400018 40. 95. 3.96 1.95 3.9 2170800400019 40. 97. 4.4 2.25 4.5 2170800400020 42. 99. 5.04 1.8 3.6 2170800400021 44. 103. 5.3 1.85 3.7 2170800400022 45. 105. 4.3 2.3 4.6 2170800400023 51. 127. 2.17 2.2 4.4 2170800400024 52. 132. 3.15 1.85 3.7 2170800400025 53. 131. 4.55 2.4 4.8 2170800400026 53. 133. 4.25 4.5 9.0 2170800400027 54. 136. 0.797 2.2 4.4 2170800400028 56. 140. 3.6 1.9 3.8 2170800400029 58. 141. 3.68 2.05 4.1 2170800400030 58. 143. 2.93 2.0 4.0 2170800400031 58. 144. 2.59 3.65 7.3 2170800400032 60. 147. 1.64 2.1 4.2 2170800400033 ENDDATA 17 0 2170800400034 ENDSUBENT 33 0 2170800499999 SUBENT 21708005 20181004 22732170800500001 BIB 4 10 2170800500002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 2170800500003 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800500004 Target diameter 14 mm, enrichment 99.9 percent U-233. 2170800500005 Isotopic ratios U-234/U-233 4.2*10**-3, 2170800500006 U-238/U-233 1.8*10**-2, U-232/U-233 2.3*10**-6. 2170800500007 STATUS (TABLE) Data taken from R,CEA-R-5147,1981 2170800500008 (SPSDD,21708009) Superseded by re-analyzed data. 2170800500009 HISTORY (19840806C) BN. 2170800500010 (20181002U) SD: ERR-T -> MISC. ERR-ANALYS deleted 2170800500011 (information moved to Subent 001). ERR-1 was added. 2170800500012 ENDBIB 10 0 2170800500013 NOCOMMON 0 0 2170800500014 DATA 5 13 2170800500015 ELEMENT MASS DATA ERR-1 MISC 2170800500016 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT 2170800500017 40. 95. 5.13 2.75 5.5 2170800500018 40. 97. 4.85 2.85 5.7 2170800500019 42. 99. 4.4 2.5 5.0 2170800500020 44. 103. 2.81 2.65 5.3 2170800500021 52. 132. 3.14 2.65 5.3 2170800500022 53. 131. 4.63 2.65 5.3 2170800500023 54. 135. 3.46 3.5 7.0 2170800500024 55. 136. 0.84 3.0 6.0 2170800500025 56. 140. 4.39 2.85 5.7 2170800500026 58. 141. 4.24 3.05 6.1 2170800500027 58. 143. 3.17 2.75 5.5 2170800500028 58. 144. 2.43 4.0 8.0 2170800500029 60. 147. 1.32 3.25 6.5 2170800500030 ENDDATA 15 0 2170800500031 ENDSUBENT 30 0 2170800599999 SUBENT 21708006 20181004 22732170800600001 BIB 7 56 2170800600002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 2170800600003 SAMPLE .U(3)-O(8) Targets on aluminum foils. 2170800600004 Diameter 14 mm, enrichment 99.9 percent U-235. 2170800600005 Isotopic ratios U-234/U-235 7.0*10**-6, 2170800600006 U-238/U-235 9.0*10**-6. 2170800600007 ANALYSIS Final value for each fission product is the combination2170800600008 of these different measurements through weighted 2170800600009 averages, the weight being defined as the inverse of 2170800600010 the square of the statistical uncertainty associated 2170800600011 with each individual measurement. 2170800600012 Old yields data were updated as: 2170800600013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800600014 w1, w2 - normalized weights corresponding to each gamma2170800600015 line: 2170800600016 95Zr 724 keV 50%, 757 keV 50%; 2170800600017 97Zr 658 keV 50%, 743 keV 50%; 2170800600018 127Sb 473 keV 50%, 686 keV 50%; 2170800600019 136Cs 818 keV 60%, 1048 keV 40%; 2170800600020 140Ba 163 keV 50%, 537 keV 50%; 2170800600021 147Nd 91 keV 50%, 531 keV 50%; 2170800600022 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800600023 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800600024 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800600025 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800600026 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800600027 89.06+-0.24 ; 2.747+-4E-4 . 2170800600028 (51-SB-127,3.850D,DG,473.0,0.258,DG,685.7,0.368) 2170800600029 25.8+-1.6 ; 3.850+-0.05 ; 36.8+-2.0. 2170800600030 (53-I-131,8.025D,DG,364.5,0.815) 2170800600031 81.5+-0.8 ; 8.025+-0.001 . 2170800600032 (53-I-133-G,0.867D,DG,529.5,0.870) 2170800600033 87.0+-3.0 ; 0.867+-0.004 . 2170800600034 (52-TE-132,3.204D,DG,228.2,0.88) 2170800600035 88+-3 ; 3.204+-0.013 . 2170800600036 (54-XE-135-G,0.381D,DG,249.8,0.90) 2170800600037 90+-3 ; 0.381+-0.001 . 2170800600038 (55-CS-136-G,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170800600039 13.04+-0.03 ; 80.+-3. . 2170800600040 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800600041 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800600042 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800600043 48.29+-0.20 ; 32.508+-0.013 . 2170800600044 (58-CE-143,1.376D,DG,293.3,0.428) 2170800600045 42.8+-0.4 ; 1.376+-0.002 . 2170800600046 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800600047 11.09+-0.19 ; 284.91+-0.05 . 2170800600048 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800600049 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800600050 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170800600051 combination of ERR-1 (see Subent 001) and nuclear data 2170800600052 uncertainties 2170800600053 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170800600054 (gamma intensity and half-life). 2170800600055 STATUS (TABLE) Table X of Nucl.Data Sheets,111(2010)2965. 2170800600056 HISTORY (20111113C) Subent was added. 2170800600057 (20181004U) SD: ERR-ANALYS was updated. 2170800600058 ENDBIB 56 0 2170800600059 NOCOMMON 0 0 2170800600060 DATA 7 15 2170800600061 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800600062 MISC 2170800600063 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800600064 PER-CENT 2170800600065 40. 95. 5.28 2.15 0.3 2.2 2170800600066 4.3 2170800600067 40. 97. 4.98 2.75 0.1 2.8 2170800600068 5.5 2170800600069 42. 99. 5.08 2.15 0.3 2.2 2170800600070 4.3 2170800600071 44. 103. 3.02 2.3 1.3 2.7 2170800600072 4.6 2170800600073 51. 127. 1.73 4.0 4.1 5.7 2170800600074 8.0 2170800600075 52. 132. 4.14 2.2 3.4 4.1 2170800600076 4.4 2170800600077 53. 131. 4.35 2.75 1.0 2.5 2170800600078 5.5 2170800600079 53. 133. 5.43 2.7 3.3 4.3 2170800600080 5.4 2170800600081 54. 135. 5.01 3.45 3.3 4.8 2170800600082 6.9 2170800600083 55. 136. 0.214 4.25 1.5 5.0 2170800600084 8.5 2170800600085 56. 140. 4.52 2.35 0.9 2.5 2170800600086 4.7 2170800600087 58. 141. 4.52 2.25 0.4 2.3 2170800600088 4.5 2170800600089 58. 143. 3.68 2.3 0.9 2.5 2170800600090 4.6 2170800600091 58. 144. 3.16 0.75 1.7 1.9 2170800600092 1.5 2170800600093 60. 147. 1.51 2.65 4.2 5.0 2170800600094 5.3 2170800600095 ENDDATA 34 0 2170800600096 ENDSUBENT 95 0 2170800699999 SUBENT 21708007 20181004 22732170800700001 BIB 7 57 2170800700002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 2170800700003 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800700004 Target diameter 14 mm, enrichment 99.9 percent U-238. 2170800700005 Isotopic ratios U-234/U-238 9.0E-6 ; 2170800700006 U-235/U-238 2.0E-6 ; U-236/U-238 5.4E-6. 2170800700007 ANALYSIS Final value for each fission product is the combination2170800700008 of these different measurements through weighted 2170800700009 averages, the weight being defined as the inverse of 2170800700010 the square of the statistical uncertainty associated 2170800700011 with each individual measurement. 2170800700012 Old yields data were updated as: 2170800700013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800700014 w1, w2 - normalized weights corresponding to each gamma2170800700015 line: 2170800700016 95Zr 724 keV 50%, 757 keV 50%; 2170800700017 97Zr 658 keV 50%, 743 keV 50%; 2170800700018 127Sb 473 keV 50%, 686 keV 50%; 2170800700019 140Ba 163 keV 50%, 537 keV 50%; 2170800700020 147Nd 91 keV 50%, 531 keV 50% . 2170800700021 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800700022 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800700023 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800700024 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800700025 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800700026 89.06+-0.24 ; 2.747+-4E-4 . 2170800700027 (44-RU-103,39.26D,DG,497.1,0.910) 2170800700028 91.0+-1.2 ; 39.26+-0.02 . 2170800700029 (45-RH-105-G,1.473D,DG,318.9,0.191) 2170800700030 19.1+-0.6 ; 1.473+-0.002. 2170800700031 (51-SB-127,3.850D,DG,473.0,0.258,DG,685.7,0.368) 2170800700032 25.8+-1.6 ; 3.850+-0.05 ; 36.8+-2.0. 2170800700033 (53-I-131,8.025D,DG,364.5,0.815) 2170800700034 81.5+-0.8 ; 8.025+-0.001 . 2170800700035 (53-I-133-G,0.867D,DG,529.5,0.870) 2170800700036 87.0+-3.0 ; 0.867+-0.004 . 2170800700037 (52-TE-132,3.204D,DG,228.2,0.88) 2170800700038 88+-3 ; 3.204+-0.013 . 2170800700039 (54-XE-135-G,0.381D,DG,249.8,0.90) 2170800700040 90+-3 ; 0.381+-0.001 . 2170800700041 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800700042 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800700043 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800700044 48.29+-0.20 ; 32.508+-0.013 . 2170800700045 (58-CE-143,1.376D,DG,293.3,0.428) 2170800700046 42.8+-0.4 ; 1.376+-0.002 . 2170800700047 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800700048 11.09+-0.19 ; 284.91+-0.05 . 2170800700049 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800700050 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800700051 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170800700052 combination of ERR-1 (see Subent 001) and nuclear data 2170800700053 uncertainties 2170800700054 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170800700055 (gamma intensity and half-life). 2170800700056 STATUS (TABLE) Table XII of Nucl.Data Sheets,111(2010)2965. 2170800700057 HISTORY (20111113C) Subent was added. 2170800700058 (20181004U) SD: ERR-ANALYS was updated. 2170800700059 ENDBIB 57 0 2170800700060 NOCOMMON 0 0 2170800700061 DATA 7 15 2170800700062 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800700063 MISC 2170800700064 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800700065 PER-CENT 2170800700066 40. 95. 4.92 2.35 0.3 2.4 2170800700067 4.7 2170800700068 40. 97. 5.18 2.65 0.1 2.7 2170800700069 5.3 2170800700070 42. 99. 5.79 2.2 0.3 2.2 2170800700071 4.4 2170800700072 44. 103. 4.64 2.25 1.3 2.6 2170800700073 4.5 2170800700074 45. 105. 3.36 3.25 3.1 4.5 2170800700075 6.5 2170800700076 51. 127. 1.35 2.85 4.1 5.0 2170800700077 5.7 2170800700078 52. 132. 4.72 2.2 3.4 4.1 2170800700079 4.4 2170800700080 53. 131. 4.08 2.4 1.0 2.6 2170800700081 4.8 2170800700082 53. 133. 5.50 3.25 3.3 4.7 2170800700083 6.5 2170800700084 54. 135. 5.74 2.75 3.3 4.3 2170800700085 5.5 2170800700086 56. 140. 4.56 2.35 0.9 2.5 2170800700087 4.7 2170800700088 58. 141. 4.45 2.25 0.4 2.3 2170800700089 4.5 2170800700090 58. 143. 3.86 2.5 0.9 2.7 2170800700091 5.0 2170800700092 58. 144. 3.73 3.75 1.7 4.1 2170800700093 7.5 2170800700094 60. 147. 1.94 2.6 4.2 4.9 2170800700095 5.2 2170800700096 ENDDATA 34 0 2170800700097 ENDSUBENT 96 0 2170800799999 SUBENT 21708008 20181004 22732170800800001 BIB 7 59 2170800800002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 2170800800003 SAMPLE .PU-O(2) Targets on aluminum foils. 2170800800004 Target diameter 14 mm, enrichment in Pu-239 2170800800005 better than 98. percent. 2170800800006 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170800800007 Pu-241/Pu-239 3.7*10**-4. 2170800800008 ANALYSIS Final value for each fission product is the combination2170800800009 of these different measurements through weighted 2170800800010 averages, the weight being defined as the inverse of 2170800800011 the square of the statistical uncertainty associated 2170800800012 with each individual measurement. 2170800800013 Old yields data were updated as: 2170800800014 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800800015 w1, w2 - normalized weights corresponding to each gamma2170800800016 line: 2170800800017 95Zr 724 keV 50%, 757 keV 50%; 2170800800018 97Zr 658 keV 50%, 743 keV 50%; 2170800800019 127Sb 473 keV 50%, 686 keV 50%; 2170800800020 136Cs 818 keV 60%, 1048 keV 40%; 2170800800021 140Ba 163 keV 50%, 537 keV 50%; 2170800800022 147Nd 91 keV 50%, 531 keV 50%; 2170800800023 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800800024 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800800025 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800800026 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800800027 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800800028 89.06+-0.24 ; 2.747+-4E-4 . 2170800800029 (44-RU-103,39.26D,DG,497.1,0.910) 2170800800030 91.0+-1.2 ; 39.26+-0.02 . 2170800800031 (45-RH-105-G,1.473D,DG,318.9,0.191) 2170800800032 19.1+-0.6 ; 1.473+-0.002. 2170800800033 (51-SB-127,3.850D,DG,473.0,0.258,DG,685.7,0.368) 2170800800034 25.8+-1.6 ; 3.850+-0.05 ; 36.8+-2.0. 2170800800035 (53-I-131,8.025D,DG,364.5,0.815) 2170800800036 81.5+-0.8 ; 8.025+-0.001 . 2170800800037 (53-I-133-G,0.867D,DG,529.5,0.870) 2170800800038 87.0+-3.0 ; 0.867+-0.004 . 2170800800039 (52-TE-132,3.204D,DG,228.2,0.88) 2170800800040 88+-3 ; 3.204+-0.013 . 2170800800041 (55-CS-136-G,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170800800042 13.04+-0.03 ; 80.+-3. . 2170800800043 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800800044 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800800045 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800800046 48.29+-0.20 ; 32.508+-0.013 . 2170800800047 (58-CE-143,1.376D,DG,293.3,0.428) 2170800800048 42.8+-0.4 ; 1.376+-0.002 . 2170800800049 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800800050 11.09+-0.19 ; 284.91+-0.05 . 2170800800051 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800800052 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800800053 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170800800054 combination of ERR-1 (see Subent 001) and nuclear data 2170800800055 uncertainties 2170800800056 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170800800057 (gamma intensity and half-life). 2170800800058 STATUS (TABLE) Table XI of Nucl.Data Sheets,111(2010)2965. 2170800800059 HISTORY (20111113C) Subent was added. 2170800800060 (20181004U) SD: ERR-ANALYS was updated. 2170800800061 ENDBIB 59 0 2170800800062 NOCOMMON 0 0 2170800800063 DATA 7 15 2170800800064 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800800065 MISC 2170800800066 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800800067 PER-CENT 2170800800068 40. 95. 3.92 2.2 0.3 2.2 2170800800069 4.4 2170800800070 40. 97. 4.36 2.5 0.1 2.5 2170800800071 5.0 2170800800072 42. 99. 5.07 2.05 0.3 2.1 2170800800073 4.1 2170800800074 44. 103. 5.12 2.05 1.3 2.5 2170800800075 4.1 2170800800076 45. 105. 4.25 2.55 3.1 4.0 2170800800077 5.1 2170800800078 51. 127. 2.13 2.45 4.1 4.8 2170800800079 4.9 2170800800080 52. 132. 3.15 2.2 3.4 4.0 2170800800081 4.4 2170800800082 53. 131. 4.58 2.65 1.0 2.8 2170800800083 5.3 2170800800084 53. 133. 4.25 4.75 3.3 5.8 2170800800085 9.5 2170800800086 54. 136. 0.79 2.45 1.5 2.9 2170800800087 4.9 2170800800088 56. 140. 3.53 2.15 0.9 2.3 2170800800089 4.3 2170800800090 58. 141. 3.69 2.3 0.4 2.3 2170800800091 4.6 2170800800092 58. 143. 2.87 2.25 0.9 2.4 2170800800093 4.5 2170800800094 58. 144. 2.60 3.9 1.7 4.3 2170800800095 7.8 2170800800096 60. 147. 1.53 2.35 4.2 4.8 2170800800097 4.7 2170800800098 ENDDATA 34 0 2170800800099 ENDSUBENT 98 0 2170800899999 SUBENT 21708009 20181004 22732170800900001 BIB 7 53 2170800900002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 2170800900003 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800900004 Target diameter 14 mm, enrichment 99.9 percent U-233. 2170800900005 Isotopic ratios U-234/U-233 4.2*10**-3, 2170800900006 U-238/U-233 1.8*10**-2, U-232/U-233 2.3*10**-6. 2170800900007 ANALYSIS Final value for each fission product is the combination2170800900008 of these different measurements through weighted 2170800900009 averages, the weight being defined as the inverse of 2170800900010 the square of the statistical uncertainty associated 2170800900011 with each individual measurement. 2170800900012 Old yields data were updated as: 2170800900013 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800900014 w1, w2 - normalized weights corresponding to each gamma2170800900015 line: 2170800900016 95Zr 724 keV 50%, 757 keV 50%; 2170800900017 97Zr 658 keV 50%, 743 keV 50%; 2170800900018 136Cs 818 keV 60%, 1048 keV 40%; 2170800900019 140Ba 163 keV 50%, 537 keV 50%; 2170800900020 147Nd 91 keV 50%, 531 keV 50%; 2170800900021 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800900022 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800900023 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800900024 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800900025 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800900026 89.06+-0.24 ; 2.747+-4E-4 . 2170800900027 (44-RU-103,39.26D,DG,497.1,0.910) 2170800900028 91.0+-1.2 ; 39.26+-0.02 . 2170800900029 (53-I-131,8.025D,DG,364.5,0.815) 2170800900030 81.5+-0.8 ; 8.025+-0.001 . 2170800900031 (52-TE-132,3.204D,DG,228.2,0.88) 2170800900032 88+-3 ; 3.204+-0.013 . 2170800900033 (54-XE-135-G,0.381D,DG,249.8,0.90) 2170800900034 90+-3 ; 0.381+-0.001 . 2170800900035 (55-CS-136-G,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170800900036 13.04+-0.03 ; 80.+-3. . 2170800900037 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800900038 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800900039 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800900040 48.29+-0.20 ; 32.508+-0.013 . 2170800900041 (58-CE-143,1.376D,DG,293.3,0.428) 2170800900042 42.8+-0.4 ; 1.376+-0.002 . 2170800900043 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800900044 11.09+-0.19 ; 284.91+-0.05 . 2170800900045 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800900046 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800900047 ERR-ANALYS (ERR-T) Total uncertainty ( 1-sigma) is quadrature 2170800900048 combination of ERR-1 (see Subent 001) and nuclear data 2170800900049 uncertainties 2170800900050 (ERR-2) Uncertainty ( 1-sigma) due to nuclear data 2170800900051 (gamma intensity and half-life). 2170800900052 STATUS (TABLE) Table VIII of Nucl.Data Sheets,111(2010)2965. 2170800900053 HISTORY (20111113C) Subent was added. 2170800900054 (20181004U) SD: ERR-ANALYS was updated. 2170800900055 ENDBIB 53 0 2170800900056 NOCOMMON 0 0 2170800900057 DATA 7 13 2170800900058 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800900059 MISC 2170800900060 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800900061 PER-CENT 2170800900062 40. 95. 5.08 3.0 0.3 3.0 2170800900063 6.0 2170800900064 40. 97. 4.80 3.1 0.1 3.1 2170800900065 6.2 2170800900066 42. 99. 4.43 2.05 0.3 2.1 2170800900067 4.1 2170800900068 44. 103. 2.75 1.9 1.3 3.1 2170800900069 3.8 2170800900070 52. 132. 3.14 1.9 3.4 3.9 2170800900071 3.8 2170800900072 53. 131. 4.66 1.9 1.0 2.3 2170800900073 3.8 2170800900074 54. 135. 3.48 3.75 3.3 5.0 2170800900075 7.5 2170800900076 55. 136. 0.83 3.25 1.5 4.9 2170800900077 6.5 2170800900078 56. 140. 4.30 3.1 0.9 3.1 2170800900079 6.2 2170800900080 58. 141. 4.25 3.3 0.4 3.3 2170800900081 6.6 2170800900082 58. 143. 3.11 3.0 0.9 3.1 2170800900083 6.0 2170800900084 58. 144. 2.44 4.25 1.7 4.5 2170800900085 8.5 2170800900086 60. 147. 1.23 3.5 4.2 7.2 2170800900087 7.0 2170800900088 ENDDATA 30 0 2170800900089 ENDSUBENT 88 0 2170800999999 ENDENTRY 9 0 2170899999999