ENTRY 21708 20111113 2170800000001 SUBENT 21708001 20111113 20120825 2170800100001 BIB 14 65 2170800100002 INSTITUTE (2FR BRC) Service Radiochimie Et Phenemologie. 2170800100003 REFERENCE (J,NDS,111,2965,2010) Re-analyzed data. 2170800100004 (R,CEA-R-5147,198112) 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 (P,NEANDC(E)-172,(4),18,1976) Abstract. 2170800100015 (P,NEANDC(E)-192,(4),28,1978) Abstract. 2170800100016 AUTHOR (J.Laurec, A.Adam, T.DeBruyne, E.Bauge, T.Granier, 2170800100017 J.Aupiais, O.Bersillon, G.LePetit, N.Authier, P.Casoli)2170800100018 TITLE Fission Product Yields of 233-U, 235-U, 238-U and 2170800100019 239-Pu in Fields of Thermal Neutrons, Fission Neutrons 2170800100020 and 14.7-MeV Neutrons. 2170800100021 FACILITY (ACCEL,2FR ITL) Lancelot electrostatic accelerator of 2170800100022 CEA-Valduc. 2170800100023 INC-SOURCE (D-T) Deuteron-tritium reaction. 2170800100024 Deuterons at a 160 KV voltage were bombarding a 2170800100025 rotating TiT water-cooled target. 2170800100026 INC-SPECT Neutron flux at 2 cm downstream from the production 2170800100027 target, on the beam axis, was on the order of 2170800100028 5*10**10 neutron/cm**2/s. 2170800100029 SAMPLE Thin deposits ( made by electroplating) - for fission 2170800100030 chambers; 2170800100031 thicker ones (made by electrospraying) - for fission 2170800100032 products analysis. 2170800100033 METHOD (CHSEP) Radiochemical method. Direct measurement of 2170800100034 the number of fissions and of the fission product 2170800100035 activities.Used for low-activity Ce-144,Eu-155,Eu-156.2170800100036 DETECTOR (FISCH) Plane fission chamber for measurement of the 2170800100037 number of fissions. 2170800100038 (GELI ) Calibrated Ge-Li spectrometers. 2170800100039 COMMENT .Target and chamber deposit masses are determined by 2170800100040 alpha and mass spectrometries. 2170800100041 ERR-ANALYS (ERR-4,0.3,6.) Statistical uncertainty of photopeak 2170800100042 area. 2170800100043 (ERR-5,1.,2.) Statistical uncertainty of samples mass 2170800100044 ratio. 2170800100045 (ERR-6) Statistical uncertainty of measurement of 2170800100046 number of fissions. 2170800100047 (ERR-7,,1.5) Statistical uncertainty of neutron flux 2170800100048 readjustment. 2170800100049 (ERR-8) Systematical uncertainty of gamma detection 2170800100050 efficiency. 2170800100051 (ERR-9) Systematical uncertainty of samples mass 2170800100052 ratio. 2170800100053 HISTORY (19810114C) G.C. 2170800100054 (19810120E) 2170800100055 (19840806A) Main reference received. 2170800100056 Data updated and U-233 data added. 2170800100057 (19850419E) 2170800100058 (19850821U)HH 2170800100059 (19860106E) 2170800100060 (20111113A) Upper -> lower case correction. 2170800100061 Dates were corrected for 4-digits year. 2170800100062 Old data were superseded by newer re-analyzed data 2170800100063 of J,NDS,111,2965,2010 . 2170800100064 CORRECTION .For the difference of the neutron flux between the 2170800100065 fission chamber and the target deposits. 2170800100066 For contribution from fissile materials. 2170800100067 ENDBIB 65 0 2170800100068 COMMON 4 3 2170800100069 EN ERR-6 ERR-8 ERR-9 2170800100070 MEV PER-CENT PER-CENT PER-CENT 2170800100071 1.4700E+01 0.5 2.0 0.8 2170800100072 ENDCOMMON 3 0 2170800100073 ENDSUBENT 72 0 2170800199999 SUBENT 21708002 20111113 20120825 2170800200001 BIB 5 14 2170800200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 2170800200003 Fission yields. 2170800200004 SAMPLE .U(3)-O(8) Targets on aluminum foils. 2170800200005 Diameter 14 mm, enrichment 99.9 percent U-235. 2170800200006 Isotopic ratios U-234/U-235 7.0*10**-6, 2170800200007 U-238/U-235 9.0*10**-6. 2170800200008 ERR-ANALYS (ERR-T) Total error given but the error due to the 2170800200009 uncertainties in the branching ratios of the 2170800200010 fission products is not included. 2170800200011 .Detailed contributions are given in Table page 35. 2170800200012 STATUS (TABLE) Data taken from R,CEA-R-5147,1981 2170800200013 (SPSDD,21708006) Superseded by re-analyzed data. 2170800200014 HISTORY (19810114C) G.C. 2170800200015 (19810120E) 2170800200016 ENDBIB 14 0 2170800200017 NOCOMMON 0 0 2170800200018 DATA 4 15 2170800200019 ELEMENT MASS DATA ERR-T 2170800200020 NO-DIM NO-DIM PC/FIS PER-CENT 2170800200021 4.0000E+01 9.5000E+01 5.3300E+00 3.8000E+00 2170800200022 4.0000E+01 9.7000E+01 5.0300E+00 5.0000E+00 2170800200023 4.2000E+01 9.9000E+01 5.0500E+00 3.8000E+00 2170800200024 4.4000E+01 1.0300E+02 3.0800E+00 4.1000E+00 2170800200025 5.1000E+01 1.2700E+02 1.7600E+00 7.5000E+00 2170800200026 5.2000E+01 1.3200E+02 4.1400E+00 3.9000E+00 2170800200027 5.3000E+01 1.3100E+02 4.3200E+00 4.0000E+00 2170800200028 5.3000E+01 1.3300E+02 5.4300E+00 4.9000E+00 2170800200029 5.4000E+01 1.3500E+02 4.9700E+00 6.4000E+00 2170800200030 5.5000E+01 1.3600E+02 2.1600E-01 9.0000E+00 2170800200031 5.6000E+01 1.4000E+02 4.6100E+00 4.2000E+00 2170800200032 5.8000E+01 1.4100E+02 4.5000E+00 4.0000E+00 2170800200033 5.8000E+01 1.4300E+02 3.7500E+00 4.1000E+00 2170800200034 5.8000E+01 1.4400E+02 3.1500E+00 1.0000E+00 2170800200035 6.0000E+01 1.4700E+02 1.6200E+00 4.8000E+00 2170800200036 ENDDATA 17 0 2170800200037 ENDSUBENT 36 0 2170800299999 SUBENT 21708003 20111113 20120825 2170800300001 BIB 5 14 2170800300002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 2170800300003 Fission yields. 2170800300004 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800300005 Target diameter 14 mm, enrichment 99.9 percent U-238. 2170800300006 Isotopic ratios U-234/U-238 9.0E-6 ; 2170800300007 U-235/U-238 2.0E-6 ; U-236/U-238 5.4E-6. 2170800300008 ERR-ANALYS (ERR-T) Total error given but the error due to the 2170800300009 uncertainties in the branching ratios of the 2170800300010 fission products is not included. 2170800300011 .Detailed contributions are given in Table page 35. 2170800300012 STATUS (TABLE) Data taken from R,CEA-R-5147,1981 2170800300013 (SPSDD,21708007) Superseded by re-analyzed data. 2170800300014 HISTORY (19810114C) G.C. 2170800300015 (19810120E) 2170800300016 ENDBIB 14 0 2170800300017 NOCOMMON 0 0 2170800300018 DATA 4 15 2170800300019 ELEMENT MASS DATA ERR-T 2170800300020 NO-DIM NO-DIM PC/FIS PER-CENT 2170800300021 4.0000E+01 9.5000E+01 4.9700E+00 4.2000E+00 2170800300022 4.0000E+01 9.7000E+01 5.2300E+00 4.8000E+00 2170800300023 4.2000E+01 9.9000E+01 5.7500E+00 3.9000E+00 2170800300024 4.4000E+01 1.0300E+02 4.7400E+00 4.0000E+00 2170800300025 4.5000E+01 1.0500E+02 3.4000E+00 6.0000E+00 2170800300026 5.1000E+01 1.2700E+02 1.3800E+00 5.2000E+00 2170800300027 5.2000E+01 1.3200E+02 4.7200E+00 3.9000E+00 2170800300028 5.3000E+01 1.3100E+02 4.0500E+00 4.3000E+00 2170800300029 5.3000E+01 1.3300E+02 5.5000E+00 6.0000E+00 2170800300030 5.4000E+01 1.3500E+02 5.7000E+00 5.0000E+00 2170800300031 5.6000E+01 1.4000E+02 4.6500E+00 4.2000E+00 2170800300032 5.8000E+01 1.4100E+02 4.4400E+00 4.0000E+00 2170800300033 5.8000E+01 1.4300E+02 3.9400E+00 4.5000E+00 2170800300034 5.8000E+01 1.4400E+02 3.7200E+00 7.0000E+00 2170800300035 6.0000E+01 1.4700E+02 2.0800E+00 4.7000E+00 2170800300036 ENDDATA 17 0 2170800300037 ENDSUBENT 36 0 2170800399999 SUBENT 21708004 20111113 20120825 2170800400001 BIB 5 15 2170800400002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 2170800400003 Fission yields. 2170800400004 SAMPLE .PU-O(2) Targets on aluminum foils. 2170800400005 Target diameter 14 mm, enrichment in Pu-239 2170800400006 better than 98. percent. 2170800400007 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170800400008 Pu-241/Pu-239 3.7*10**-4. 2170800400009 ERR-ANALYS (ERR-T) Total error given but the error due to the 2170800400010 uncertainties in the branching ratios of the 2170800400011 fission products is not included. 2170800400012 .Detailed contributions are given in Table page 35. 2170800400013 STATUS (TABLE) Data taken from R,CEA-R-5147,1981 2170800400014 (SPSDD,21708008) Superseded by re-analyzed data. 2170800400015 HISTORY (19810114C) G.C. 2170800400016 (19810120E) 2170800400017 ENDBIB 15 0 2170800400018 NOCOMMON 0 0 2170800400019 DATA 4 15 2170800400020 ELEMENT MASS DATA ERR-T 2170800400021 NO-DIM NO-DIM PC/FIS PER-CENT 2170800400022 4.0000E+01 9.5000E+01 3.9600E+00 3.9000E+00 2170800400023 4.0000E+01 9.7000E+01 4.4000E+00 4.5000E+00 2170800400024 4.2000E+01 9.9000E+01 5.0400E+00 3.6000E+00 2170800400025 4.4000E+01 1.0300E+02 5.3000E+00 3.7000E+00 2170800400026 4.5000E+01 1.0500E+02 4.3000E+00 4.6000E+00 2170800400027 5.1000E+01 1.2700E+02 2.1700E+00 4.4000E+00 2170800400028 5.2000E+01 1.3200E+02 3.1500E+00 3.7000E+00 2170800400029 5.3000E+01 1.3100E+02 4.5500E+00 4.8000E+00 2170800400030 5.3000E+01 1.3300E+02 4.2500E+00 9.0000E+00 2170800400031 5.4000E+01 1.3600E+02 7.9700E-01 4.4000E+00 2170800400032 5.6000E+01 1.4000E+02 3.6000E+00 3.8000E+00 2170800400033 5.8000E+01 1.4100E+02 3.6800E+00 4.1000E+00 2170800400034 5.8000E+01 1.4300E+02 2.9300E+00 4.0000E+00 2170800400035 5.8000E+01 1.4400E+02 2.5900E+00 7.3000E+00 2170800400036 6.0000E+01 1.4700E+02 1.6400E+00 4.2000E+00 2170800400037 ENDDATA 17 0 2170800400038 ENDSUBENT 37 0 2170800499999 SUBENT 21708005 20111113 20120825 2170800500001 BIB 5 14 2170800500002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 2170800500003 Fission yields. 2170800500004 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800500005 Target diameter 14 mm, enrichment 99.9 percent U-233. 2170800500006 Isotopic ratios U-234/U-233 4.2*10**-3, 2170800500007 U-238/U-233 1.8*10**-2, U-232/U-233 2.3*10**-6. 2170800500008 ERR-ANALYS (ERR-T) Total error given but the error due to the 2170800500009 uncertainties in the branching ratios of the 2170800500010 fission products is not included. 2170800500011 .Detailed contributions are given in Table page 35. 2170800500012 STATUS (TABLE) Data taken from R,CEA-R-5147,1981 2170800500013 (SPSDD,21708009) Superseded by re-analyzed data. 2170800500014 HISTORY (19840806C) BN. 2170800500015 (19850419E) 2170800500016 ENDBIB 14 0 2170800500017 NOCOMMON 0 0 2170800500018 DATA 4 13 2170800500019 ELEMENT MASS DATA ERR-T 2170800500020 NO-DIM NO-DIM PC/FIS PER-CENT 2170800500021 4.0000E+01 9.5000E+01 5.1300E+00 5.5000E+00 2170800500022 4.0000E+01 9.7000E+01 4.8500E+00 5.7000E+00 2170800500023 4.2000E+01 9.9000E+01 4.4000E+00 5.0000E+00 2170800500024 4.4000E+01 1.0300E+02 2.8100E+00 5.3000E+00 2170800500025 5.2000E+01 1.3200E+02 3.1400E+00 5.3000E+00 2170800500026 5.3000E+01 1.3100E+02 4.6300E+00 5.3000E+00 2170800500027 5.4000E+01 1.3500E+02 3.4600E+00 7.0000E+00 2170800500028 5.5000E+01 1.3600E+02 8.3700E-01 6.0000E+00 2170800500029 5.6000E+01 1.4000E+02 4.3900E+00 5.7000E+00 2170800500030 5.8000E+01 1.4100E+02 4.2400E+00 6.1000E+00 2170800500031 5.8000E+01 1.4300E+02 3.1700E+00 5.5000E+00 2170800500032 5.8000E+01 1.4400E+02 2.4300E+00 8.0000E+00 2170800500033 6.0000E+01 1.4700E+02 1.3200E+00 6.5000E+00 2170800500034 ENDDATA 15 0 2170800500035 ENDSUBENT 34 0 2170800599999 SUBENT 21708006 20111113 20120825 2170800600001 BIB 8 64 2170800600002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) 2170800600003 Fission yields. 2170800600004 SAMPLE .U(3)-O(8) Targets on aluminum foils. 2170800600005 Diameter 14 mm, enrichment 99.9 percent U-235. 2170800600006 Isotopic ratios U-234/U-235 7.0*10**-6, 2170800600007 U-238/U-235 9.0*10**-6. 2170800600008 ANALYSIS Final value for each fission product is the combination2170800600009 of these different measurements through weighted 2170800600010 averages, the weight being defined as the inverse of 2170800600011 the square of the statistical uncertainty associated 2170800600012 with each individual measurement. 2170800600013 Old yields data were updated as: 2170800600014 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800600015 w1, w2 - normalized weights corresponding to each gamma2170800600016 line: 2170800600017 95Zr 724 keV 50%, 757 keV 50%; 2170800600018 97Zr 658 keV 50%, 743 keV 50%; 2170800600019 127Sb 473 keV 50%, 686 keV 50%; 2170800600020 136Cs 818 keV 60%, 1048 keV 40%; 2170800600021 140Ba 163 keV 50%, 537 keV 50%; 2170800600022 147Nd 91 keV 50%, 531 keV 50%; 2170800600023 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800600024 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800600025 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800600026 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800600027 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800600028 89.06+-0.24 ; 2.747+-4E-4 . 2170800600029 (51-SB-127,3.850D,DG,473.0,0.258,DG,685.7,0.368) 2170800600030 25.8+-1.6 ; 3.850+-0.05 ; 36.8+-2.0. 2170800600031 (53-I-131,8.025D,DG,364.5,0.815) 2170800600032 81.5+-0.8 ; 8.025+-0.001 . 2170800600033 (53-I-133,0.867D,DG,529.5,0.870) 2170800600034 87.0+-3.0 ; 0.867+-0.004 . 2170800600035 (52-TE-132,3.204D,DG,228.2,0.88) 2170800600036 88+-3 ; 3.204+-0.013 . 2170800600037 (54-XE-135,0.381D,DG,249.8,0.90) 2170800600038 90+-3 ; 0.381+-0.001 . 2170800600039 (55-CS-136,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170800600040 13.04+-0.03 ; 80.+-3. . 2170800600041 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800600042 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800600043 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800600044 48.29+-0.20 ; 32.508+-0.013 . 2170800600045 (58-CE-143,1.376D,DG,293.3,0.428) 2170800600046 42.8+-0.4 ; 1.376+-0.002 . 2170800600047 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800600048 11.09+-0.19 ; 284.91+-0.05 . 2170800600049 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800600050 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800600051 ERR-ANALYS (ERR-T) Total uncertainty ( 1 sigma) as combination 2170800600052 in quadrature of: 2170800600053 (ERR-1) Uncertainty (2 sigma) associated with 2170800600054 measurements, i.e. combination of statistical and 2170800600055 systematic uncertainty; 2170800600056 derived from authors' errors - see MISC-COL. 2170800600057 (ERR-2) Uncertainty ( 1 sigma) due to nuclear data. 2170800600058 MISC-COL (MISC) Uncertainty (2 sigma) associated with 2170800600059 measurements, i.e. combination of statistical and 2170800600060 systematic uncertainty, given by authors in article. 2170800600061 Were re-calculated (/2.) as ERR-1 to obtain 1 sigma 2170800600062 error; authors' errors are given as MISC according to 2170800600063 the comment of N.Otsuka (NDS,IAEA) . 2170800600064 STATUS (TABLE) Table X of J,NDS,111,2965,201081 2170800600065 HISTORY (20111113C) Subent was added. 2170800600066 ENDBIB 64 0 2170800600067 NOCOMMON 0 0 2170800600068 DATA 7 15 2170800600069 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800600070 MISC 2170800600071 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800600072 PER-CENT 2170800600073 40. 95. 5.28 2.15 0.3 2.2 2170800600074 4.3 2170800600075 40. 97. 4.98 2.75 0.1 2.8 2170800600076 5.5 2170800600077 42. 99. 5.08 2.15 0.3 2.2 2170800600078 4.3 2170800600079 44. 103. 3.02 2.3 1.3 2.7 2170800600080 4.6 2170800600081 51. 127. 1.73 4.0 4.1 5.7 2170800600082 8.0 2170800600083 52. 132. 4.14 2.2 3.4 4.1 2170800600084 4.4 2170800600085 53. 131. 4.35 2.75 1.0 2.5 2170800600086 5.5 2170800600087 53. 133. 5.43 2.7 3.3 4.3 2170800600088 5.4 2170800600089 54. 135. 5.01 3.45 3.3 4.8 2170800600090 6.9 2170800600091 55. 136. 0.214 4.25 1.5 5.0 2170800600092 8.5 2170800600093 56. 140. 4.52 2.35 0.9 2.5 2170800600094 4.7 2170800600095 58. 141. 4.52 2.25 0.4 2.3 2170800600096 4.5 2170800600097 58. 143. 3.68 2.3 0.9 2.5 2170800600098 4.6 2170800600099 58. 144. 3.16 0.75 1.7 1.9 2170800600100 1.5 2170800600101 60. 147. 1.51 2.65 4.2 5.0 2170800600102 5.3 2170800600103 ENDDATA 34 0 2170800600104 ENDSUBENT 103 0 2170800699999 SUBENT 21708007 20111113 20120825 2170800700001 BIB 8 65 2170800700002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 2170800700003 Fission yields. 2170800700004 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800700005 Target diameter 14 mm, enrichment 99.9 percent U-238. 2170800700006 Isotopic ratios U-234/U-238 9.0E-6 ; 2170800700007 U-235/U-238 2.0E-6 ; U-236/U-238 5.4E-6. 2170800700008 ANALYSIS Final value for each fission product is the combination2170800700009 of these different measurements through weighted 2170800700010 averages, the weight being defined as the inverse of 2170800700011 the square of the statistical uncertainty associated 2170800700012 with each individual measurement. 2170800700013 Old yields data were updated as: 2170800700014 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800700015 w1, w2 - normalized weights corresponding to each gamma2170800700016 line: 2170800700017 95Zr 724 keV 50%, 757 keV 50%; 2170800700018 97Zr 658 keV 50%, 743 keV 50%; 2170800700019 127Sb 473 keV 50%, 686 keV 50%; 2170800700020 140Ba 163 keV 50%, 537 keV 50%; 2170800700021 147Nd 91 keV 50%, 531 keV 50% . 2170800700022 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800700023 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800700024 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800700025 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800700026 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800700027 89.06+-0.24 ; 2.747+-4E-4 . 2170800700028 (44-RU-103,39.26D,DG,497.1,0.910) 2170800700029 91.0+-1.2 ; 39.26+-0.02 . 2170800700030 (45-RH-105,1.473D,DG,318.9,0.191) 2170800700031 19.1+-0.6 ; 1.473+-0.002. 2170800700032 (51-SB-127,3.850D,DG,473.0,0.258,DG,685.7,0.368) 2170800700033 25.8+-1.6 ; 3.850+-0.05 ; 36.8+-2.0. 2170800700034 (53-I-131,8.025D,DG,364.5,0.815) 2170800700035 81.5+-0.8 ; 8.025+-0.001 . 2170800700036 (53-I-133,0.867D,DG,529.5,0.870) 2170800700037 87.0+-3.0 ; 0.867+-0.004 . 2170800700038 (52-TE-132,3.204D,DG,228.2,0.88) 2170800700039 88+-3 ; 3.204+-0.013 . 2170800700040 (54-XE-135,0.381D,DG,249.8,0.90) 2170800700041 90+-3 ; 0.381+-0.001 . 2170800700042 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800700043 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800700044 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800700045 48.29+-0.20 ; 32.508+-0.013 . 2170800700046 (58-CE-143,1.376D,DG,293.3,0.428) 2170800700047 42.8+-0.4 ; 1.376+-0.002 . 2170800700048 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800700049 11.09+-0.19 ; 284.91+-0.05 . 2170800700050 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800700051 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800700052 ERR-ANALYS (ERR-T) Total uncertainty ( 1 sigma) as combination 2170800700053 in quadrature of: 2170800700054 (ERR-1) Uncertainty (2 sigma) associated with 2170800700055 measurements, i.e. combination of statistical and 2170800700056 systematic uncertainty; 2170800700057 derived from authors' errors - see MISC-COL. 2170800700058 (ERR-2) Uncertainty ( 1 sigma) due to nuclear data. 2170800700059 MISC-COL (MISC) Uncertainty (2 sigma) associated with 2170800700060 measurements, i.e. combination of statistical and 2170800700061 systematic uncertainty, given by authors in article. 2170800700062 Were re-calculated (/2.) as ERR-1 to obtain 1 sigma 2170800700063 error; authors' errors are given as MISC according to 2170800700064 the comment of N.Otsuka (NDS,IAEA) . 2170800700065 STATUS (TABLE) Table XII of J,NDS,111,2965,201081 2170800700066 HISTORY (20111113C) Subent was added. 2170800700067 ENDBIB 65 0 2170800700068 NOCOMMON 0 0 2170800700069 DATA 7 15 2170800700070 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800700071 MISC 2170800700072 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800700073 PER-CENT 2170800700074 40. 95. 4.92 2.35 0.3 2.4 2170800700075 4.7 2170800700076 40. 97. 5.18 2.65 0.1 2.7 2170800700077 5.3 2170800700078 42. 99. 5.79 2.2 0.3 2.2 2170800700079 4.4 2170800700080 44. 103. 4.64 2.25 1.3 2.6 2170800700081 4.5 2170800700082 45. 105. 3.36 3.25 3.1 4.5 2170800700083 6.5 2170800700084 51. 127. 1.35 2.85 4.1 5.0 2170800700085 5.7 2170800700086 52. 132. 4.72 2.2 3.4 4.1 2170800700087 4.4 2170800700088 53. 131. 4.08 2.4 1.0 2.6 2170800700089 4.8 2170800700090 53. 133. 5.50 3.25 3.3 4.7 2170800700091 6.5 2170800700092 54. 135. 5.74 2.75 3.3 4.3 2170800700093 5.5 2170800700094 56. 140. 4.56 2.35 0.9 2.5 2170800700095 4.7 2170800700096 58. 141. 4.45 2.25 0.4 2.3 2170800700097 4.5 2170800700098 58. 143. 3.86 2.5 0.9 2.7 2170800700099 5.0 2170800700100 58. 144. 3.73 3.75 1.7 4.1 2170800700101 7.5 2170800700102 60. 147. 1.94 2.6 4.2 4.9 2170800700103 5.2 2170800700104 ENDDATA 34 0 2170800700105 ENDSUBENT 104 0 2170800799999 SUBENT 21708008 20111113 20120825 2170800800001 BIB 8 67 2170800800002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY) 2170800800003 Fission yields. 2170800800004 SAMPLE .PU-O(2) Targets on aluminum foils. 2170800800005 Target diameter 14 mm, enrichment in Pu-239 2170800800006 better than 98. percent. 2170800800007 Isotopic ratios Pu-240/Pu-239 1.71*10**-2, 2170800800008 Pu-241/Pu-239 3.7*10**-4. 2170800800009 ANALYSIS Final value for each fission product is the combination2170800800010 of these different measurements through weighted 2170800800011 averages, the weight being defined as the inverse of 2170800800012 the square of the statistical uncertainty associated 2170800800013 with each individual measurement. 2170800800014 Old yields data were updated as: 2170800800015 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800800016 w1, w2 - normalized weights corresponding to each gamma2170800800017 line: 2170800800018 95Zr 724 keV 50%, 757 keV 50%; 2170800800019 97Zr 658 keV 50%, 743 keV 50%; 2170800800020 127Sb 473 keV 50%, 686 keV 50%; 2170800800021 136Cs 818 keV 60%, 1048 keV 40%; 2170800800022 140Ba 163 keV 50%, 537 keV 50%; 2170800800023 147Nd 91 keV 50%, 531 keV 50%; 2170800800024 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800800025 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800800026 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800800027 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800800028 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800800029 89.06+-0.24 ; 2.747+-4E-4 . 2170800800030 (44-RU-103,39.26D,DG,497.1,0.910) 2170800800031 91.0+-1.2 ; 39.26+-0.02 . 2170800800032 (45-RH-105,1.473D,DG,318.9,0.191) 2170800800033 19.1+-0.6 ; 1.473+-0.002. 2170800800034 (51-SB-127,3.850D,DG,473.0,0.258,DG,685.7,0.368) 2170800800035 25.8+-1.6 ; 3.850+-0.05 ; 36.8+-2.0. 2170800800036 (53-I-131,8.025D,DG,364.5,0.815) 2170800800037 81.5+-0.8 ; 8.025+-0.001 . 2170800800038 (53-I-133,0.867D,DG,529.5,0.870) 2170800800039 87.0+-3.0 ; 0.867+-0.004 . 2170800800040 (52-TE-132,3.204D,DG,228.2,0.88) 2170800800041 88+-3 ; 3.204+-0.013 . 2170800800042 (55-CS-136,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170800800043 13.04+-0.03 ; 80.+-3. . 2170800800044 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800800045 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800800046 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800800047 48.29+-0.20 ; 32.508+-0.013 . 2170800800048 (58-CE-143,1.376D,DG,293.3,0.428) 2170800800049 42.8+-0.4 ; 1.376+-0.002 . 2170800800050 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800800051 11.09+-0.19 ; 284.91+-0.05 . 2170800800052 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800800053 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800800054 ERR-ANALYS (ERR-T) Total uncertainty ( 1 sigma) as combination 2170800800055 in quadrature of: 2170800800056 (ERR-1) Uncertainty (2 sigma) associated with 2170800800057 measurements, i.e. combination of statistical and 2170800800058 systematic uncertainty; 2170800800059 derived from authors' errors - see MISC-COL. 2170800800060 (ERR-2) Uncertainty ( 1 sigma) due to nuclear data. 2170800800061 MISC-COL (MISC) Uncertainty (2 sigma) associated with 2170800800062 measurements, i.e. combination of statistical and 2170800800063 systematic uncertainty, given by authors in article. 2170800800064 Were re-calculated (/2.) as ERR-1 to obtain 1 sigma 2170800800065 error; authors' errors are given as MISC according to 2170800800066 the comment of N.Otsuka (NDS,IAEA) . 2170800800067 STATUS (TABLE) Table XI of J,NDS,111,2965,201081 2170800800068 HISTORY (20111113C) Subent was added. 2170800800069 ENDBIB 67 0 2170800800070 NOCOMMON 0 0 2170800800071 DATA 7 15 2170800800072 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800800073 MISC 2170800800074 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800800075 PER-CENT 2170800800076 40. 95. 3.92 2.2 0.3 2.2 2170800800077 4.4 2170800800078 40. 97. 4.36 2.5 0.1 2.5 2170800800079 5.0 2170800800080 42. 99. 5.07 2.05 0.3 2.1 2170800800081 4.1 2170800800082 44. 103. 5.12 2.05 1.3 2.5 2170800800083 4.1 2170800800084 45. 105. 4.25 2.55 3.1 4.0 2170800800085 5.1 2170800800086 51. 127. 2.13 2.45 4.1 4.8 2170800800087 4.9 2170800800088 52. 132. 3.15 2.2 3.4 4.0 2170800800089 4.4 2170800800090 53. 131. 4.58 2.65 1.0 2.8 2170800800091 5.3 2170800800092 53. 133. 4.25 4.75 3.3 5.8 2170800800093 9.5 2170800800094 54. 136. 0.79 2.45 1.5 2.9 2170800800095 4.9 2170800800096 56. 140. 3.53 2.15 0.9 2.3 2170800800097 4.3 2170800800098 58. 141. 3.69 2.3 0.4 2.3 2170800800099 4.6 2170800800100 58. 143. 2.87 2.25 0.9 2.4 2170800800101 4.5 2170800800102 58. 144. 2.60 3.9 1.7 4.3 2170800800103 7.8 2170800800104 60. 147. 1.53 2.35 4.2 4.8 2170800800105 4.7 2170800800106 ENDDATA 34 0 2170800800107 ENDSUBENT 106 0 2170800899999 SUBENT 21708009 20111113 20120825 2170800900001 BIB 8 61 2170800900002 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) 2170800900003 Fission yields. 2170800900004 SAMPLE .U(3)-O(8) targets on aluminum foils. 2170800900005 Target diameter 14 mm, enrichment 99.9 percent U-233. 2170800900006 Isotopic ratios U-234/U-233 4.2*10**-3, 2170800900007 U-238/U-233 1.8*10**-2, U-232/U-233 2.3*10**-6. 2170800900008 ANALYSIS Final value for each fission product is the combination2170800900009 of these different measurements through weighted 2170800900010 averages, the weight being defined as the inverse of 2170800900011 the square of the statistical uncertainty associated 2170800900012 with each individual measurement. 2170800900013 Old yields data were updated as: 2170800900014 Y-new=Y-old(w1*(I1-old/I1-new)+w2*(I2-old/I2-new)), 2170800900015 w1, w2 - normalized weights corresponding to each gamma2170800900016 line: 2170800900017 95Zr 724 keV 50%, 757 keV 50%; 2170800900018 97Zr 658 keV 50%, 743 keV 50%; 2170800900019 136Cs 818 keV 60%, 1048 keV 40%; 2170800900020 140Ba 163 keV 50%, 537 keV 50%; 2170800900021 147Nd 91 keV 50%, 531 keV 50%; 2170800900022 DECAY-DATA (40-ZR-95,64.032D,DG,724.2,0.4427,DG,756.7,0.5438) 2170800900023 44.27+-0.22; 64.032+-0.006; 54.38+-0.22. 2170800900024 (40-ZR-97,0.698D,DG,657.9,0.9823,DG,743.4,0.9309) 2170800900025 98.23+-0.08; 0.698+-3E-4; 93.09+-0.16 . 2170800900026 (42-MO-99,2.747D,DG,140.5,0.8906) 2170800900027 89.06+-0.24 ; 2.747+-4E-4 . 2170800900028 (44-RU-103,39.26D,DG,497.1,0.910) 2170800900029 91.0+-1.2 ; 39.26+-0.02 . 2170800900030 (53-I-131,8.025D,DG,364.5,0.815) 2170800900031 81.5+-0.8 ; 8.025+-0.001 . 2170800900032 (52-TE-132,3.204D,DG,228.2,0.88) 2170800900033 88+-3 ; 3.204+-0.013 . 2170800900034 (54-XE-135,0.381D,DG,249.8,0.90) 2170800900035 90+-3 ; 0.381+-0.001 . 2170800900036 (55-CS-136,13.04D,DG,818.5,0.9970,DG,1048.1,0.80) 2170800900037 13.04+-0.03 ; 80.+-3. . 2170800900038 (56-BA-140,12.753D,DG,162.7,0.0622,DG,537.2,0.02439) 2170800900039 6.22+-0.09 ; 12.753+-0.002 ; 24.39+-0.22 . 2170800900040 (58-CE-141,32.508D,DG,145.4,0.4829) 2170800900041 48.29+-0.20 ; 32.508+-0.013 . 2170800900042 (58-CE-143,1.376D,DG,293.3,0.428) 2170800900043 42.8+-0.4 ; 1.376+-0.002 . 2170800900044 (58-CE-144,284.91D,DG,133.5,0.1109) 2170800900045 11.09+-0.19 ; 284.91+-0.05 . 2170800900046 (60-ND-147,10.98D,DG,91.0,0.281,DG,531.0,0.1337) 2170800900047 28.1+-0.5 ; 10.98+-0.01 ; 13.37+-1.1 . 2170800900048 ERR-ANALYS (ERR-T) Total uncertainty ( 1 sigma) as combination 2170800900049 in quadrature of: 2170800900050 (ERR-1) Uncertainty (2 sigma) associated with 2170800900051 measurements, i.e. combination of statistical and 2170800900052 systematic uncertainty; 2170800900053 derived from authors' errors - see MISC-COL. 2170800900054 (ERR-2) Uncertainty ( 1 sigma) due to nuclear data. 2170800900055 MISC-COL (MISC) Uncertainty (2 sigma) associated with 2170800900056 measurements, i.e. combination of statistical and 2170800900057 systematic uncertainty, given by authors in article. 2170800900058 Were re-calculated (/2.) as ERR-1 to obtain 1 sigma 2170800900059 error; authors' errors are given as MISC according to 2170800900060 the comment of N.Otsuka (NDS,IAEA) . 2170800900061 STATUS (TABLE) Table VIII of J,NDS,111,2965,201081 2170800900062 HISTORY (20111113C) Subent was added. 2170800900063 ENDBIB 61 0 2170800900064 NOCOMMON 0 0 2170800900065 DATA 7 13 2170800900066 ELEMENT MASS DATA ERR-1 ERR-2 ERR-T 2170800900067 MISC 2170800900068 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 2170800900069 PER-CENT 2170800900070 40. 95. 5.08 3.0 0.3 3.0 2170800900071 6.0 2170800900072 40. 97. 4.80 3.1 0.1 3.1 2170800900073 6.2 2170800900074 42. 99. 4.43 2.05 0.3 2.1 2170800900075 4.1 2170800900076 44. 103. 2.75 1.9 1.3 3.1 2170800900077 3.8 2170800900078 52. 132. 3.14 1.9 3.4 3.9 2170800900079 3.8 2170800900080 53. 131. 4.66 1.9 1.0 2.3 2170800900081 3.8 2170800900082 54. 135. 3.48 3.75 3.3 5.0 2170800900083 7.5 2170800900084 55. 136. 0.83 3.25 1.5 4.9 2170800900085 6.5 2170800900086 56. 140. 4.30 3.1 0.9 3.1 2170800900087 6.2 2170800900088 58. 141. 4.25 3.3 0.4 3.3 2170800900089 6.6 2170800900090 58. 143. 3.11 3.0 0.9 3.1 2170800900091 6.0 2170800900092 58. 144. 2.44 4.25 1.7 4.5 2170800900093 8.5 2170800900094 60. 147. 1.23 3.5 4.2 7.2 2170800900095 7.0 2170800900096 ENDDATA 30 0 2170800900097 ENDSUBENT 96 0 2170800999999 ENDENTRY 9 0 2170899999999