ENTRY 13340 20190506 14511334000000001 SUBENT 13340001 20190506 14511334000100001 BIB 10 54 1334000100002 TITLE Mass distributions for the spontaneous fission of 1334000100003 253Es and the thermal-neutron-induced fission of 254Es 1334000100004 AUTHOR (K.F.Flynn,J.E.Gindler,L.E.Glendenin,R.K.Sjoblom) 1334000100005 REFERENCE (J,JIN,38,661,1976) 1334000100006 #doi:10.1016/0022-1902(76)80333-8 1334000100007 #NSR: 1976FL03 1334000100008 (R,ANL-7996,8,1973) The same data for spontaneous 1334000100009 fission of 253Es as main ref., data for 1334000100010 thermal-neutron-induced fission of 255Fm and 251Cf 1334000100011 included in EXFOR #10516. 1334000100012 #NSR: 1973FLZQ 1334000100013 REL-REF (O,10516001,K.F.Flynn+,J,PR/C,11,1676,1975) 1334000100014 INSTITUTE (1USAANL) 1334000100015 SAMPLE The einsteinium isotopes used for these studies were 1334000100016 obtained from the Transuranium Element Production 1334000100017 Program at Oak Ridge National Laboratory. The 1334000100018 einsteinium was chemically separated from other 1334000100019 actinide and fission product elements by elution with 1334000100020 a-hydroxyisobutryric acid from a Dowex-50 cation 1334000100021 exchange resin column(ammonium form). After removal of 1334000100022 small aliquots for alpha counting, the purified sources1334000100023 of einsteinium were deposited on platinum discs. 1334000100024 DETECTOR (GELI) 17-cm3 coaxial lithium-drifted germanium 1334000100025 detector. 1334000100026 METHOD (CHSEP,GSPEC) The catcher foils were dissolved in the 1334000100027 presence of carriers, specific fission products were 1334000100028 radiochemically purified and thick samples(~10mg/cm2) 1334000100029 were mounted for beta counting in calibrated low 1334000100030 background (0.4 count/min) counting equipment. The 1334000100031 radioactive purity of each sample was verified by 1334000100032 following its decay over several half lives. The 1334000100033 observed counting rate for each fission product was 1334000100034 corrected for chemical yield, counter efficiency, 1334000100035 decay, genetic relationships and degree of saturation 1334000100036 to give the relative saturation activity A which is 1334000100037 proportional to the fission yield. In several 1334000100038 experiments the activities of various fission 1334000100039 products were determined without chemical separation 1334000100040 by measuring the gamma-ray spectrum from the catcher 1334000100041 foils with a lithium-drifted germanium detector. 1334000100042 These spectra were analyzed with a computer program 1334000100043 to determine the relative intensity of the various 1334000100044 gamma-rays. 1334000100045 ANALYSIS The relative fission yields determined by these 1334000100046 methods were placed on an absolute basis by 1334000100047 normalizing the final mass-yield curves to 200% total 1334000100048 yield. 1334000100049 HISTORY (19891023C) VM 1334000100050 (20170807A) BP: Updated to new date formats,lower 1334000100051 case. Corrections according last EXFOR rules and 1334000100052 Dict. Added more experimental details, doi and nubar 1334000100053 data per cpd871 recommendations. 1334000100054 (20190506U) OG. 2nd reference was added. 1334000100055 #NSR was added. 1334000100056 ENDBIB 54 0 1334000100057 NOCOMMON 0 0 1334000100058 ENDSUBENT 57 0 1334000199999 SUBENT 13340002 20170807 14301334000200001 BIB 3 7 1334000200002 REACTION (99-ES-253(0,F)ELEM/MASS,CUM,FY) 1334000200003 ERR-ANALYS (DATA-ERR) The error for each fission yield value was 1334000200004 estimated on the basis of the number of measurements, 1334000200005 errors in the determination of relative saturation 1334000200006 activity (A), and any uncertainties in the decay 1334000200007 scheme of the particular nuclide measured. 1334000200008 STATUS (TABLE) Table 1, page 662. 1334000200009 ENDBIB 7 0 1334000200010 NOCOMMON 0 0 1334000200011 DATA 5 33 1334000200012 MASS ELEMENT ISOMER DATA DATA-ERR 1334000200013 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 1334000200014 83. 35. 0.061 0.006 1334000200015 89. 38. 0.366 0.037 1334000200016 91. 38. 0.528 0.037 1334000200017 93. 39. 0.674 0.067 1334000200018 95. 40. 1.13 0.20 1334000200019 97. 40. 1.84 0.09 1334000200020 99. 42. 3.09 0.15 1334000200021 103. 44. 5.83 0.29 1334000200022 105. 44. 6.18 0.93 1334000200023 106. 44. 6.45 0.48 1334000200024 109. 46. 5.47 0.55 1334000200025 111. 47. 4.69 0.24 1334000200026 112. 46. 3.77 0.38 1334000200027 115. 48. 0. 2.61 0.13 1334000200028 115. 48. 1. 0.212 0.012 1334000200029 121. 50. 0. 0.139 0.014 1334000200030 125. 50. 0. 0.00918 0.0009 1334000200031 127. 51. 0.0639 0.006 1334000200032 129. 51. 0.313 0.024 1334000200033 131. 53. 1.15 0.12 1334000200034 132. 52. 2.40 0.24 1334000200035 133. 53. 2.68 0.27 1334000200036 135. 53. 3.90 0.39 1334000200037 139. 56. 5.93 0.60 1334000200038 140. 56. 5.62 0.28 1334000200039 141. 58. 5.81 0.58 1334000200040 143. 58. 6.48 0.32 1334000200041 144. 58. 5.16 0.52 1334000200042 149. 61. 3.17 0.32 1334000200043 151. 61. 1.93 0.19 1334000200044 153. 62. 1.50 0.15 1334000200045 157. 63. 0.75 0.08 1334000200046 159. 64. 0.57 0.06 1334000200047 ENDDATA 35 0 1334000200048 ENDSUBENT 47 0 1334000299999 SUBENT 13340003 20170807 14301334000300001 BIB 3 8 1334000300002 REACTION (99-ES-253(0,F)MASS,CHN,FY) 1334000300003 ERR-ANALYS (DATA-ERR) The error for each fission yield value was 1334000300004 estimated on the basis of the number of measurements, 1334000300005 errors in the determination of relative saturation 1334000300006 activity (A), and any uncertainties in the decay 1334000300007 scheme of the particular nuclide measured. 1334000300008 STATUS (DEP,13340002) 1334000300009 (TABLE) Table 1, page 662. 1334000300010 ENDBIB 8 0 1334000300011 NOCOMMON 0 0 1334000300012 DATA 3 3 1334000300013 MASS DATA DATA-ERR 1334000300014 NO-DIM PC/FIS PC/FIS 1334000300015 115. 2.82 0.14 1334000300016 121. 0.160 0.016 1334000300017 125. 0.0193 0.002 1334000300018 ENDDATA 5 0 1334000300019 ENDSUBENT 18 0 1334000399999 SUBENT 13340004 20170807 14301334000400001 BIB 4 9 1334000400002 REACTION (99-ES-254(N,F)ELEM/MASS,CUM,FY,,MXW) 1334000400003 FACILITY (REAC,1USAANL) CP-5 research reactor: neutron flux of 1334000400004 about 2x10**13 neutrons cm-2 sec-1. 1334000400005 ERR-ANALYS (DATA-ERR) The error for each fission yield value was 1334000400006 estimated on the basis of the number of measurements, 1334000400007 errors in the determination of relative saturation 1334000400008 activity (A), and any uncertainties in the decay 1334000400009 scheme of the particular nuclide measured. 1334000400010 STATUS (TABLE) Table 1, page 662. 1334000400011 ENDBIB 9 0 1334000400012 COMMON 1 3 1334000400013 EN-DUMMY 1334000400014 EV 1334000400015 0.0253 1334000400016 ENDCOMMON 3 0 1334000400017 DATA 5 30 1334000400018 MASS ELEMENT ISOMER DATA DATA-ERR 1334000400019 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 1334000400020 89. 38. 0.053 0.008 1334000400021 91. 38. 0.28 0.03 1334000400022 95. 40. 0.72 0.07 1334000400023 97. 40. 0.99 0.10 1334000400024 99. 42. 2.34 0.18 1334000400025 103. 44. 3.15 0.32 1334000400026 105. 44. 4.29 0.43 1334000400027 106. 44. 4.07 0.41 1334000400028 109. 46. 3.76 0.56 1334000400029 111. 47. 4.23 0.21 1334000400030 112. 46. 4.40 0.44 1334000400031 113. 47. 0. 3.49 0.35 1334000400032 115. 48. 0. 5.34 0.53 1334000400033 115. 48. 1. 0.30 0.03 1334000400034 121. 50. 0. 2.54 0.15 1334000400035 125. 50. 0. 0.447 0.05 1334000400036 127. 51. 0.95 0.10 1334000400037 129. 51. 1.94 0.20 1334000400038 131. 53. 3.84 0.38 1334000400039 132. 52. 4.76 0.48 1334000400040 133. 53. 5.09 0.76 1334000400041 135. 53. 5.31 0.80 1334000400042 140. 56. 4.01 0.20 1334000400043 141. 58. 4.63 0.36 1334000400044 143. 58. 4.89 0.40 1334000400045 144. 58. 3.92 0.39 1334000400046 151. 61. 1.73 0.34 1334000400047 153. 62. 1.62 0.32 1334000400048 156. 62. 0.80 0.16 1334000400049 157. 63. 0.76 0.11 1334000400050 ENDDATA 32 0 1334000400051 ENDSUBENT 50 0 1334000499999 SUBENT 13340005 20170807 14301334000500001 BIB 4 10 1334000500002 REACTION (99-ES-254(N,F)MASS,CHN,FY,,MXW) 1334000500003 FACILITY (REAC,1USAANL) CP-5 research reactor: neutron flux of 1334000500004 about 2x10**13 neutrons cm-2 sec-1. 1334000500005 ERR-ANALYS (DATA-ERR) The error for each fission yield value was 1334000500006 estimated on the basis of the number of measurements, 1334000500007 errors in the determination of relative saturation 1334000500008 activity (A), and any uncertainties in the decay 1334000500009 scheme of the particular nuclide measured. 1334000500010 STATUS (DEP,13340004) 1334000500011 (TABLE) Table 1, page 662. 1334000500012 ENDBIB 10 0 1334000500013 COMMON 1 3 1334000500014 EN-DUMMY 1334000500015 EV 1334000500016 0.0253 1334000500017 ENDCOMMON 3 0 1334000500018 DATA 3 4 1334000500019 MASS DATA DATA-ERR 1334000500020 NO-DIM PC/FIS PC/FIS 1334000500021 113. 4.72 0.47 1334000500022 115. 5.64 0.56 1334000500023 121. 2.92 0.29 1334000500024 125. 0.9493 0.10 1334000500025 ENDDATA 6 0 1334000500026 ENDSUBENT 25 0 1334000599999 SUBENT 13340006 20170814 14301334000600001 BIB 4 8 1334000600002 REACTION (99-ES-253(0,F),,NU) 1334000600003 ANALYSIS Derived from the mean masses (first moments) of the 1334000600004 light and heavy mass groups (AL and AH) as nubar = 1334000600005 AF-(AL+AH), where AF is the mass of the compound 1334000600006 nucleus for the particular fissioning system. 1334000600007 STATUS (DEP,13340002) 1334000600008 (TABLE) Table 2, page 663. 1334000600009 HISTORY (20170814C) BP 1334000600010 ENDBIB 8 0 1334000600011 NOCOMMON 0 0 1334000600012 DATA 1 1 1334000600013 DATA 1334000600014 PRT/FIS 1334000600015 4.7 1334000600016 ENDDATA 3 0 1334000600017 ENDSUBENT 16 0 1334000699999 SUBENT 13340007 20170814 14301334000700001 BIB 5 10 1334000700002 REACTION (99-ES-254(N,F),,NU) 1334000700003 FACILITY (REAC,1USAANL) CP-5 research reactor: neutron flux of 1334000700004 about 2x10**13 neutrons cm-2 sec-1. 1334000700005 ANALYSIS Derived from the mean masses (first moments) of the 1334000700006 light and heavy mass groups (AL and AH) as nubar = 1334000700007 AF-(AL+AH), where AF is the mass of the compound 1334000700008 nucleus for the particular fissioning system. 1334000700009 STATUS (DEP,13340004) 1334000700010 (TABLE) Table 2, page 663. 1334000700011 HISTORY (20170814C) BP 1334000700012 ENDBIB 10 0 1334000700013 COMMON 1 3 1334000700014 EN 1334000700015 EV 1334000700016 0.0253 1334000700017 ENDCOMMON 3 0 1334000700018 DATA 1 1 1334000700019 DATA 1334000700020 PRT/FIS 1334000700021 4.2 1334000700022 ENDDATA 3 0 1334000700023 ENDSUBENT 22 0 1334000799999 ENDENTRY 7 0 1334099999999