ENTRY 31686 20100114 31443168600000001 SUBENT 31686001 20100114 31443168600100001 BIB 9 12 3168600100002 TITLE Fission yield measurements by inductively coupled 3168600100003 plasma mass-spectrometry 3168600100004 AUTHOR (I.Glagolenko, B.Hilton, J.Giglio, D.Cummings) 3168600100005 INSTITUTE (1USAINL) 3168600100006 REFERENCE (J,JRN,282,651,2009) 3168600100007 INC-SOURCE (REAC) 3168600100008 METHOD (AMS) Inductively Coupled Plasma Mass Spectrometry 3168600100009 ERR-ANALYS (ERR-T) 1 sigma converted from 2 sigma by compiler 3168600100010 (ERR-1) Uncertainty due to spectrometry (5% at 2 sigma)3168600100011 STATUS (APRVD) Irina Glagolenko (2010-01-14) 3168600100012 HISTORY (20091117C) On 3168600100013 (20100114A) On. Approved by authors. 3168600100014 ENDBIB 12 0 3168600100015 COMMON 1 3 3168600100016 ERR-1 3168600100017 PER-CENT 3168600100018 2.5 3168600100019 ENDCOMMON 3 0 3168600100020 ENDSUBENT 19 0 3168600199999 SUBENT 31686002 20091117 31433168600200001 BIB 7 10 3168600200002 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 3168600200003 2(92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 3168600200004 MONITOR 1(92-U-235(N,F)39-Y-89,CUM,FY) 3168600200005 2(92-U-235(N,F)57-LA-139,CUM,FY) 3168600200006 FACILITY (REAC,1USAINL) B-11 of thermal Advanced Test Reactor 3168600200007 INC-SPECT Peak thermal neutron flux: ~1.1e+14 n/cm2 at 110 MWth 3168600200008 SAMPLE 6 U-Mo metal alloy plates (44 and 58% enriched U-235).3168600200009 Compiled data are average from 6 U-Mo plates. 3168600200010 ANALYSIS More than 99% of all fissions came from U-235. 3168600200011 STATUS (TABLE) Table 1 of J,JRN,282,651,2009 (2 sigma given) 3168600200012 ENDBIB 10 0 3168600200013 COMMON 3 3 3168600200014 EN-DUMMY MONIT 1MONIT 2 3168600200015 EV PC/FIS PC/FIS 3168600200016 0.0253 4.73 6.41 3168600200017 ENDCOMMON 3 0 3168600200018 DATA 6 17 3168600200019 MASS ELEMENT DATA 1ERR-T 1DATA 2ERR-T 23168600200020 NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS PC/FIS 3168600200021 87. 37. 2.65 0.04 2.57 0.04 3168600200022 89. 39. 4.73 0.07 4.58 0.07 3168600200023 99. 43. 5.99 0.09 5.80 0.09 3168600200024 101. 44. 5.09 0.08 4.93 0.07 3168600200025 102. 44. 4.20 0.07 4.07 0.06 3168600200026 103. 45. 2.92 0.05 2.83 0.04 3168600200027 104. 44. 1.94 0.03 1.88 0.03 3168600200028 106. 46. 0.419 0.007 0.408 0.007 3168600200029 128. 52. 0.372 0.006 0.360 0.005 3168600200030 139. 57. 6.62 0.10 6.41 0.10 3168600200031 140. 58. 6.48 0.10 6.27 0.09 3168600200032 141. 59. 5.97 0.09 5.78 0.09 3168600200033 142. 58. 6.16 0.09 5.96 0.09 3168600200034 144. 60. 5.37 0.08 5.20 0.08 3168600200035 145. 60. 3.79 0.06 3.67 0.06 3168600200036 146. 60. 3.08 0.05 2.99 0.05 3168600200037 148. 60. 1.82 0.03 1.76 0.03 3168600200038 ENDDATA 19 0 3168600200039 ENDSUBENT 38 0 3168600299999 SUBENT 31686003 20100114 31443168600300001 BIB 8 47 3168600300002 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY,,FST) 3168600300003 2(92-U-235(N,F)ELEM/MASS,CUM,FY,,FST) 3168600300004 MONITOR 1((MONIT)92-U-235(N,F)57-LA-139,CUM,FY) 3168600300005 2((MONIT)92-U-235(N,F)60-ND-148,CUM,FY) 3168600300006 FACILITY (REAC,1USAINL) Row 5 of Experimental Breeder Reactor II3168600300007 INC-SPECT Peak fast neutron flux: ~1.6e+15 n/cm2. 3168600300008 Energy Dependent Neutron Flux Fraction (Position 5C1 3168600300009 in EBR-II) is tabulated below. 3168600300010 : lethargy mean energy 3168600300011 --------------------------------------------------- 3168600300012 E, low E, up fraction 3168600300013 Grp (eV) (eV) (eV) in group >E, low 3168600300014 --------------------------------------------------- 3168600300015 1 6.065E+06 1.419E+07 9.278E+06 5.17E-03 5.17E-03 3168600300016 2 3.679E+06 6.065E+06 4.724E+06 2.41E-02 2.92E-02 3168600300017 3 2.231E+06 3.679E+06 2.865E+06 5.86E-02 8.78E-02 3168600300018 4 1.353E+06 2.231E+06 1.738E+06 9.48E-02 1.83E-01 3168600300019 5 8.209E+05 1.353E+06 1.054E+06 1.22E-01 3.05E-01 3168600300020 6 4.979E+05 8.209E+05 6.393E+05 1.54E-01 4.59E-01 3168600300021 7 3.020E+05 4.979E+05 3.877E+05 1.60E-01 6.19E-01 3168600300022 8 1.832E+05 3.020E+05 2.352E+05 1.22E-01 7.41E-01 3168600300023 9 1.111E+05 1.832E+05 1.426E+05 1.02E-01 8.43E-01 3168600300024 10 6.738E+04 1.111E+05 8.652E+04 6.35E-02 9.06E-01 3168600300025 11 4.087E+04 6.738E+04 5.248E+04 4.16E-02 9.48E-01 3168600300026 12 2.479E+04 4.087E+04 3.183E+04 2.10E-02 9.69E-01 3168600300027 13 1.503E+04 2.479E+04 1.930E+04 1.45E-02 9.84E-01 3168600300028 14 9.119E+03 1.503E+04 1.171E+04 9.25E-03 9.93E-01 3168600300029 15 5.531E+03 9.119E+03 7.102E+03 3.43E-03 9.96E-01 3168600300030 16 3.355E+03 5.531E+03 4.307E+03 1.41E-03 9.98E-01 3168600300031 17 2.035E+03 3.355E+03 2.613E+03 4.45E-04 9.98E-01 3168600300032 18 1.234E+03 2.035E+03 1.585E+03 1.25E-03 9.99E-01 3168600300033 19 7.485E+02 1.234E+03 9.611E+02 4.41E-04 1.00E+00 3168600300034 20 4.540E+02 7.485E+02 5.829E+02 1.23E-04 1.00E+00 3168600300035 21 2.754E+02 4.540E+02 3.536E+02 6.00E-05 1.00E+00 3168600300036 22 1.670E+02 2.754E+02 2.145E+02 1.65E-05 1.00E+00 3168600300037 23 1.013E+02 1.670E+02 1.301E+02 7.26E-06 1.00E+00 3168600300038 24 6.144E+01 1.013E+02 7.889E+01 3.93E-06 1.00E+00 3168600300039 25 3.727E+01 6.144E+01 4.785E+01 7.85E-07 1.00E+00 3168600300040 26 2.260E+01 3.727E+01 2.902E+01 2.07E-07 1.00E+00 3168600300041 27 1.371E+01 2.260E+01 1.760E+01 1.06E-07 1.00E+00 3168600300042 28 2.500E-02 1.371E+01 5.854E-01 4.18E-08 1.00E+00 3168600300043 --------------------------------------------------- 3168600300044 SAMPLE 4 U-Zr metal alloy rods (78% enriched U-235) 3168600300045 Compiled data are average from 4 U-Zr rods. 3168600300046 ANALYSIS More than 98% of all fissions came from U-235 3168600300047 STATUS (TABLE) Table 2 of J,JRN,282,651,2009 (2 sigma given) 3168600300048 HISTORY (20100114A) On. Spectrum table form authors added. 3168600300049 ENDBIB 47 0 3168600300050 COMMON 3 3 3168600300051 EN-DUMMY MONIT 1MONIT 2 3168600300052 MEV PC/FIS PC/FIS 3168600300053 1.0 6.34 1.68 3168600300054 ENDCOMMON 3 0 3168600300055 DATA 6 17 3168600300056 MASS ELEMENT DATA 1ERR-T 1DATA 2ERR-T 23168600300057 NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS PC/FIS 3168600300058 99. 43. 6.11 0.11 6.17 0.11 3168600300059 101. 44. 5.38 0.10 5.43 0.10 3168600300060 102. 44. 4.43 0.08 4.47 0.08 3168600300061 103. 45. 3.27 0.06 3.30 0.06 3168600300062 139. 57. 6.34 0.12 6.40 0.12 3168600300063 140. 58. 6.01 0.11 6.06 0.11 3168600300064 141. 59. 5.83 0.11 5.89 0.11 3168600300065 142. 58. 5.37 0.10 5.43 0.10 3168600300066 143. 60. 5.74 0.11 5.80 0.11 3168600300067 144. 60. 5.25 0.10 5.30 0.10 3168600300068 145. 60. 3.75 0.07 3.79 0.07 3168600300069 146. 60. 2.92 0.06 2.95 0.06 3168600300070 147. 62. 2.24 0.04 2.26 0.04 3168600300071 148. 60. 1.66 0.03 1.68 0.03 3168600300072 149. 62. 1.03 0.02 1.04 0.02 3168600300073 151. 63. 0.441 0.008 0.436 0.008 3168600300074 152. 62. 0.289 0.005 0.286 0.005 3168600300075 ENDDATA 19 0 3168600300076 ENDSUBENT 75 0 3168600399999 ENDENTRY 3 0 3168699999999