ENTRY 14555 20200101 146114555 0 1 SUBENT 14555001 20191217 146114555 1 1 BIB 14 153 14555 1 2 TITLE Energy dependence of fission product yields from 235U, 14555 1 3 238U and 239Pu for incident neutron energies between 14555 1 4 0.5 and 14.8 MeV 14555 1 5 AUTHOR (M.E.Gooden,C.W.Arnold,J.A.Becker,C.Bhatia,M.Bhike, 14555 1 6 E.M.Bond, T.A.Bredeweg,B.Fallin,M.M.Fowler,C.R.Howell, 14555 1 7 J.H.Kelley, Krishichayan,R.Macri,G.Rusev,C.Ryan, 14555 1 8 S.A.Sheets,M.A.Stoyer, A.P.Tonchev,W.Tornow, 14555 1 9 D.J.Vieira,J.B.Wilhelmy) 14555 1 10 INSTITUTE (1USALAS,1USALRL,1CANMCM,1USADKE,1USATNL,1USANCS) 14555 1 11 REFERENCE (J,NDS,131,319,2016) 14555 1 12 #doi:10.1016/j.nds.2015.12.006 14555 1 13 #NSR: 2016GO02 14555 1 14 (J,NDS,119,324,2014) Prelim. data for 4.6,9.0,14.5 MeV.14555 1 15 #doi:10.1016/j.nds.2014.08.089 14555 1 16 #NSR: 2014BH11 14555 1 17 (J,EPJ/CS,146,04024,2017) Cumulative fission product 14555 1 18 yields for 147Nd (presented in figs.) 14555 1 19 #doi:10.1051/epjconf/201714604024 14555 1 20 #NSR: 2017GOZW 14555 1 21 #doi:10.1103/PhysRevC.91.064604 14555 1 22 #NSR: 2015BH09 14555 1 23 REL-REF (O,14423001,C.Bhatia+,J,PR/C,91,064604,2015) Data for 14555 1 24 8.9 MeV included in Entry 14423. 14555 1 25 FACILITY (VDGT,1USATNL) Experiments performed at the Triangle 14555 1 26 Universities Nuclear Laboratory on the campus of Duke 14555 1 27 University using a 10 MV FN Tandem Van de Graaff 14555 1 28 accelerator. 14555 1 29 DETECTOR (FISCH) Each measurement used a single dual-fission 14555 1 30 chamber placed in close proximity to the neutron 14555 1 31 production source. A special mounting was created to 14555 1 32 allow fine adjustments of the position of the fission 14555 1 33 chamber relative to the end of the beam line. Using a 14555 1 34 fixed spacer, 15.8 mm wide, the fission chambers were 14555 1 35 set a fixed distance from the end of the beam line. 14555 1 36 Finally, a fixed telescope downstream at 0 degree, 14555 1 37 was used to adjust the horizontal and vertical 14555 1 38 positioning of the chamber so that it was centered on 14555 1 39 the same position as the neutron production source. 14555 1 40 This enabled reproducible positioning of the fission 14555 1 41 chambers between different measurements. Since 235U 14555 1 42 and 239Pu have substantial thermal cross sections, a 14555 1 43 cadmium cover(hat) was made that fit over the top of 14555 1 44 the fission chambers. The Cd-hat reduces the 14555 1 45 room-return neutrons by approximately a factor of 2. 14555 1 46 A BC-501A liquid scintillator neutron detector was also14555 1 47 placed about 3 m downstream from the neutron 14555 1 48 production source which served as flux monitor and was 14555 1 49 used during neutron time-of-flight measurements. 14555 1 50 A single dual-fission chamber (DFC) contains a thick 14555 1 51 activation target and two thin reference foils of the 14555 1 52 same isotope. The body of each DFC has an outer 14555 1 53 diameter of 2.50 cm and an overall thickness of 14555 1 54 1.73 cm. The total volume of the DFC is about 3.5 cm3. 14555 1 55 The efficiency of the FCs were determined by preparing 14555 1 56 252Cf sources in the same configuration as the 14555 1 57 reference foils. The fission detection efficiency was 14555 1 58 98.5%. 14555 1 59 (HPGE) Gamma rays from fission products were measured 14555 1 60 using lead-shielded High-Purity Germanium detectors 14555 1 61 over a period of 1.5-2 months after activation using 14555 1 62 a number of different counting cycles. 14555 1 63 METHOD (ACTIV) Fission yields were determined by activation 14555 1 64 method using characteristic gamma rays of fission 14555 1 65 products. 14555 1 66 INC-SOURCE (P-LI7) The 7Li(p,n) 7Be reaction was used to achieve 14555 1 67 about 0.5 MeV neutrons. For incident proton energies 14555 1 68 greater than 2.372 MeV, the 7Li(p,n)7Be reaction is no 14555 1 69 longer monoenergetic, due to the opening of the neutron14555 1 70 emission channel from the first excited state of 7Be 14555 1 71 at 429 keV. Neutron production targets for this 14555 1 72 reaction were produced by evaporation of lithium 14555 1 73 fluoride (LiF) powder onto 19 mm diameter by 0.2 mm 14555 1 74 thick aluminum disks. The mass of the LiF varied 14555 1 75 between 0.9 and 1.2 mg between the various targets that14555 1 76 were produced. The mean incident neutron energy 14555 1 77 achieved on target using this reaction was 0.56 MeV 14555 1 78 with a total spread in neutron energy of +-30 keV. 14555 1 79 (P-T) The 3H(p,n) 3He reaction produces monoenergetic 14555 1 80 neutrons up to incident proton energies of 8.348 MeV, 14555 1 81 resulting in a maximum neutron energy of 7.7 MeV. For 14555 1 82 these measurements, this reaction was used to produce 14555 1 83 neutrons at about 1.37, 2.37 and 3.60 MeV, with total 14555 1 84 energy spreads of +-120, 70 and 70 keV respectively. 14555 1 85 The tritiated target consists of a 19 mm diameter by 14555 1 86 0.4 mm thick Cu disk on which a 16 mm diameter and 14555 1 87 2.2 mg/cm2 thick layer of titanium was evaporated. 14555 1 88 Into the Ti layer 2.1 Ci of tritium was absorbed, 14555 1 89 giving a ratio of T/Ti >1.5. In order to provide 14555 1 90 cooling to the Havar foil and tritiated target, a 14555 1 91 helium gas buffer cell (usually pressurized to about 14555 1 92 1.5 atm) is used upstream from the production target 14555 1 93 foil. The Cu disk and the copper target chamber are 14555 1 94 cooled from the outside with separate gas lines of 14555 1 95 both compressed and chilled air. For proton beam 14555 1 96 currents between 2 and 4 mu-A, a water cooled target 14555 1 97 chamber made of copper was used in place of the 14555 1 98 stainless steel target chamber. 14555 1 99 (D-D) The reaction 2H(d,n) 3He was used to produce 14555 1 100 neutrons with energies of 4.56, 5.5 and 8.9 MeV. The 14555 1 101 measurements at these energies had spreads (FWHM) in 14555 1 102 the neutron energy of +-250, 140 and 100 keV, 14555 1 103 respectively. 14555 1 104 (D-T) The 3H(d,n) 4He reaction was used to produce 14555 1 105 neutrons at the nearby energy of 14.8 MeV with an 14555 1 106 energy spread of +-75 keV. 14555 1 107 DECAY-DATA ((1.)38-SR-91,9.63HR,DG,1024.3,0.335) 14555 1 108 ((2.)38-SR-92,2.611HR,DG,1383.93,0.90) 14555 1 109 ((3.)40-ZR-95,64.032D,DG,724.192,0.4427) 14555 1 110 ((4.)40-ZR-97,16.749HR,DG,743.36,0.9309) 14555 1 111 ((5.)42-MO-99,65.976HR,DG,739.500,0.1226) 14555 1 112 ((6.)44-RU-103,39.247D,DG,497.09,0.910) 14555 1 113 ((7.)44-RU-105,4.44HR,DG,724.30,0.473) 14555 1 114 ((8.)51-SB-127,3.85D,DG,685.7,0.368) 14555 1 115 ((9.)53-I-131,8.0252D,DG,364.489,0.815) 14555 1 116 ((10.)52-TE-132,3.204D,DG,228.16,0.88) 14555 1 117 ((11.)53-I-133-G,20.83HR,DG,529.872,0.870) 14555 1 118 ((12.)54-XE-135-G,9.14HR,DG,249.794,0.90) 14555 1 119 ((14.)56-BA-140,12.7527D,DG,537.261,0.2439) 14555 1 120 ((15.)58-CE-143,33.039HR,DG,293.266,0.428) 14555 1 121 ((16.)60-ND-147,10.98D,DG,531.016,0.1337) 14555 1 122 ERR-ANALYS The following partial uncertainties are not included in14555 1 123 the total uncertainty (<1% for each): 14555 1 124 half-life, counting time, decay time, irradiation time14555 1 125 room-return neutron backgrounds. 14555 1 126 (ERR-T) The total uncertainty is determined by summing 14555 1 127 in quadrature the different components listed below. 14555 1 128 (ERR-1,0.2,6.) photo-peak area 14555 1 129 (ERR-2,0.01,0.5) neutron flux correction 14555 1 130 1(ERR-3,2.,5.) HPGe efficiency 14555 1 131 (ERR-4) fission chamber efficiency (1.5%) 14555 1 132 (ERR-5,0.1,5.4) gamma-ray emission probability 14555 1 133 (ERR-6) target positioning correction (~1%) 14555 1 134 (ERR-7) gamma-ray absorption (1.06%) 14555 1 135 (ERR-8,0.01,0.04) target mass 14555 1 136 (ERR-9,2.,4.) coincidence summing 14555 1 137 (ERR-10,0.,2.) neutron backgrounds (off-energy) 14555 1 138 2(ERR-3,0.1,0.2) efficiency ratio 14555 1 139 (ERR-4) gamma-ray absorption (0.2%) 14555 1 140 CORRECTION Data were corrected for 14555 1 141 1) Dead time correction (1%). 14555 1 142 2) The photon self-attenuation correction for each 14555 1 143 identified fission product for each target at the far 14555 1 144 (5 cm) counting position. 14555 1 145 3) An average correction for fluctuations in the 14555 1 146 neutron flux during irradiation for each fission 14555 1 147 product. 14555 1 148 COMMENT In the text in Nucl.Data Sh.,131,319,2016 on p.322 14555 1 149 for 7Li(p,n)7Be reaction: 'The mean incident neutron 14555 1 150 energy achieved on target using this reaction was 14555 1 151 0.56 MeV and marks the lowest energy data point in this14555 1 152 set of measurements'. In the tables this energy is 14555 1 153 equal 0.58 MeV. This value was used by compiler. 14555 1 154 HISTORY (20191210C) OG. 14555 1 155 ENDBIB 153 0 14555 1 156 COMMON 4 3 14555 1 157 ERR-4 1ERR-6 1ERR-7 1ERR-4 2 14555 1 158 PER-CENT PER-CENT PER-CENT PER-CENT 14555 1 159 1.5 1. 1.06 0.2 14555 1 160 ENDCOMMON 3 0 14555 1 161 ENDSUBENT 160 0 14555 199999 SUBENT 14555002 20191217 146114555 2 1 BIB 4 39 14555 2 2 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY) 14555 2 3 2((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 14555 2 4 (92-U-235(N,F)42-MO-99,CUM,FY)) 14555 2 5 SAMPLE Enriched 235U sample with mass 233.02+-0.02 mg 14555 2 6 and diameter 12.35+-0.05 mm 14555 2 7 (92-U-235,ENR=0.9327) 14555 2 8 (92-U-234,ENR=0.0105) 14555 2 9 (92-U-238,ENR=0.0568) 14555 2 10 CORRECTION 1. Corrections to the fission chamber counts due to 14555 2 11 attenuation of the neutron flux through the various 14555 2 12 components of the dual-fission chambers: 14555 2 13 En=0.56 MeV 0.07%, En=1.37 MeV 0.13%, 14555 2 14 En=2.37 MeV 0.16%, En=3.60 MeV 0.19%, 14555 2 15 En=4.49 MeV 0.18%, En=14.8 MeV 0.18%. 14555 2 16 The uncertainty on these corrections is on the order of14555 2 17 0.01%. 14555 2 18 2. Corrections to the fission chamber counts due to 14555 2 19 the kinematic focusing of the fission fragments emitted14555 2 20 by the monitor foil in each chamber: 14555 2 21 En=0.56 MeV 0.4%, En=1.37 MeV 0.6%, 14555 2 22 En=2.37 MeV 0.8%, En=3.60 MeV 1.0%, 14555 2 23 En=4.49 MeV 1.1%, En=14.8 MeV 1.5%(FC1),2.0%(FC2). 14555 2 24 3. Correction factor Rg=Measured eff./Standard eff. 14555 2 25 due to errors in positioning of the activated target in14555 2 26 the counting setup for gamma-ray spectroscopy: 14555 2 27 En=0.58 MeV 1.0307, En=1.37 MeV 1.0096, 14555 2 28 En=2.37 MeV 1.0307, En=3.60 MeV 1.0163, 14555 2 29 En=4.52 MeV 1.0343, En=14.8 MeV 1.0230. 14555 2 30 The uncertainty in R for all values about 1%. 14555 2 31 4. Corrections to the fission chamber counts due to 14555 2 32 off-energy neutrons for the 2.37 MeV data point: 14555 2 33 R=1.000, FC2 cor.=0.964+-0.002, FC1 cor.=0.961+-0.002. 14555 2 34 5. Corrections to the fission chamber counts due to 14555 2 35 off-energy neutrons for the 3.60 MeV data point: 14555 2 36 R=1.000, FC2 cor.=0.755+-0.002, FC1 cor.=0.761+-0.002. 14555 2 37 6. The isotopic corrections to the 235U fission 14555 2 38 product yields due to the 238U isotopic contribution in14555 2 39 the target. 14555 2 40 STATUS (TABLE) Tabs.XX and XXIII in Nucl.Data Sh.,131,319,201614555 2 41 ENDBIB 39 0 14555 2 42 NOCOMMON 0 0 14555 2 43 DATA 9 87 14555 2 44 EN EN-RSL-FW ELEMENT MASS DATA 1ERR-T 114555 2 45 DATA 2ERR-T 2DECAY-FLAG 14555 2 46 MEV KEV NO-DIM NO-DIM PC/FIS PC/FIS 14555 2 47 NO-DIM NO-DIM NO-DIM 14555 2 48 0.58 30. 38. 91. 5.83 0.26 14555 2 49 0.985 0.016 1. 14555 2 50 0.58 30. 38. 92. 5.96 0.34 14555 2 51 1.007 0.020 2. 14555 2 52 0.58 30. 40. 95. 6.22 0.25 14555 2 53 1.051 0.024 3. 14555 2 54 0.58 30. 40. 97. 6.05 0.18 14555 2 55 1.022 0.016 4. 14555 2 56 0.58 30. 42. 99. 5.92 0.24 14555 2 57 5. 14555 2 58 0.58 30. 44. 103. 3.18 0.11 14555 2 59 0.537 0.010 6. 14555 2 60 0.58 30. 44. 105. 1.06 0.08 14555 2 61 0.179 0.005 7. 14555 2 62 0.58 30. 51. 127. 0.20 0.01 14555 2 63 0.033 0.001 8. 14555 2 64 0.58 30. 52. 132. 4.8 0.26 14555 2 65 0.811 0.050 10. 14555 2 66 0.58 30. 53. 131. 3.12 0.11 14555 2 67 0.527 0.017 9. 14555 2 68 0.58 30. 53. 133. 6.97 0.28 14555 2 69 1.178 0.020 11. 14555 2 70 0.58 30. 54. 135. 7.01 0.38 14555 2 71 1.184 0.070 12. 14555 2 72 0.58 30. 56. 140. 5.78 0.19 14555 2 73 0.976 0.017 14. 14555 2 74 0.58 30. 58. 143. 5.84 0.24 14555 2 75 0.986 0.048 15. 14555 2 76 0.58 30. 60. 147. 2.16 0.09 14555 2 77 0.364 0.009 16. 14555 2 78 1.37 120. 38. 91. 4.99 0.22 14555 2 79 0.865 0.016 1. 14555 2 80 1.37 120. 38. 92. 5.19 0.30 14555 2 81 0.900 0.023 2. 14555 2 82 1.37 120. 40. 97. 5.65 0.016 14555 2 83 0.979 0.016 4. 14555 2 84 1.37 120. 42. 99. 5.77 0.023 14555 2 85 5. 14555 2 86 1.37 120. 44. 105. 0.96 0.06 14555 2 87 0.166 0.003 7. 14555 2 88 1.37 120. 51. 127. 0.20 0.01 14555 2 89 0.035 0.001 8. 14555 2 90 1.37 120. 52. 132. 4.49 0.25 14555 2 91 0.779 0.048 10. 14555 2 92 1.37 120. 53. 131. 3.02 0.11 14555 2 93 0.524 0.018 9. 14555 2 94 1.37 120. 53. 133. 6.22 0.25 14555 2 95 1.079 0.023 11. 14555 2 96 1.37 120. 54. 135. 6.46 0.34 14555 2 97 1.120 0.067 12. 14555 2 98 1.37 120. 56. 140. 5.81 0.18 14555 2 99 1.007 0.018 14. 14555 2 100 1.37 120. 58. 143. 5.49 0.23 14555 2 101 0.952 0.048 15. 14555 2 102 1.37 120. 60. 147. 2.17 0.08 14555 2 103 0.376 0.007 16. 14555 2 104 2.37 70. 38. 91. 5.38 0.25 14555 2 105 0.933 0.014 1. 14555 2 106 2.37 70. 38. 92. 5.36 0.30 14555 2 107 0.930 0.016 2. 14555 2 108 2.37 70. 40. 95. 6.10 0.21 14555 2 109 1.059 0.016 3. 14555 2 110 2.37 70. 40. 97. 5.94 0.20 14555 2 111 1.032 0.017 4. 14555 2 112 2.37 70. 42. 99. 5.76 0.24 14555 2 113 0.546 0.010 5. 14555 2 114 2.37 70. 44. 103. 3.15 0.12 14555 2 115 0.546 0.010 6. 14555 2 116 2.37 70. 44. 105. 1.51 0.16 14555 2 117 0.263 0.005 7. 14555 2 118 2.37 70. 51. 127. 0.33 0.02 14555 2 119 0.057 0.001 8. 14555 2 120 2.37 70. 52. 132. 4.79 0.26 14555 2 121 0.831 0.051 10. 14555 2 122 2.37 70. 53. 131. 3.23 0.12 14555 2 123 0.560 0.018 9. 14555 2 124 2.37 70. 53. 133. 6.42 0.27 14555 2 125 1.113 0.019 11. 14555 2 126 2.37 70. 54. 135. 6.48 0.36 14555 2 127 1.125 0.067 12. 14555 2 128 2.37 70. 56. 140. 5.57 0.19 14555 2 129 0.966 0.016 14. 14555 2 130 2.37 70. 58. 143. 5.36 0.23 14555 2 131 0.930 0.045 15. 14555 2 132 2.37 70. 60. 147. 2.20 0.11 14555 2 133 0.382 0.008 16. 14555 2 134 3.60 70. 38. 91. 5.42 0.24 14555 2 135 0.900 0.011 1. 14555 2 136 3.60 70. 38. 92. 5.74 0.34 14555 2 137 0.952 0.013 2. 14555 2 138 3.60 70. 40. 95. 6.02 0.18 14555 2 139 1.000 0.028 3. 14555 2 140 3.60 70. 40. 97. 6.06 0.17 14555 2 141 1.006 0.028 4. 14555 2 142 3.60 70. 42. 99. 6.03 0.25 14555 2 143 5. 14555 2 144 3.60 70. 44. 103. 3.15 0.12 14555 2 145 0.517 0.017 6. 14555 2 146 3.60 70. 44. 105. 1.63 0.07 14555 2 147 0.270 0.008 7. 14555 2 148 3.60 70. 51. 127. 0.49 0.03 14555 2 149 0.082 0.003 8. 14555 2 150 3.60 70. 52. 132. 4.84 0.27 14555 2 151 0.803 0.065 10. 14555 2 152 3.60 70. 53. 131. 3.42 0.15 14555 2 153 0.568 0.034 9. 14555 2 154 3.60 70. 53. 133. 6.49 0.26 14555 2 155 1.078 0.033 11. 14555 2 156 3.60 70. 54. 135. 6.20 0.36 14555 2 157 1.029 0.087 12. 14555 2 158 3.60 70. 56. 140. 5.36 0.22 14555 2 159 0.889 0.027 14. 14555 2 160 3.60 70. 58. 143. 5.07 0.25 14555 2 161 0.841 0.068 15. 14555 2 162 3.60 70. 60. 147. 1.96 0.08 14555 2 163 0.326 0.010 16. 14555 2 164 4.49 250. 38. 91. 5.00 0.25 14555 2 165 0.889 0.014 1. 14555 2 166 4.49 250. 38. 92. 5.11 0.31 14555 2 167 0.909 0.017 2. 14555 2 168 4.49 250. 40. 97. 5.92 0.23 14555 2 169 1.052 0.017 4. 14555 2 170 4.49 250. 42. 99. 5.63 0.28 14555 2 171 0.586 0.010 5. 14555 2 172 4.49 250. 44. 103. 3.30 0.18 14555 2 173 0.255 0.004 6. 14555 2 174 4.49 250. 44. 105. 1.44 0.13 14555 2 175 0.122 0.002 7. 14555 2 176 4.49 250. 51. 127. 0.69 0.05 14555 2 177 0.662 0.021 8. 14555 2 178 4.49 250. 52. 132. 4.90 0.30 14555 2 179 0.870 0.053 10. 14555 2 180 4.49 250. 53. 131. 3.72 0.16 14555 2 181 0.662 0.021 9. 14555 2 182 4.49 250. 53. 133. 6.27 0.30 14555 2 183 1.114 0.019 11. 14555 2 184 4.49 250. 54. 135. 6.45 0.39 14555 2 185 1.147 0.068 12. 14555 2 186 4.49 250. 56. 140. 5.29 0.21 14555 2 187 0.940 0.016 14. 14555 2 188 4.49 250. 58. 143. 4.71 0.23 14555 2 189 0.837 0.041 15. 14555 2 190 4.49 250. 60. 147. 2.06 0.11 14555 2 191 0.367 0.009 16. 14555 2 192 14.8 75. 38. 91. 4.34 0.22 14555 2 193 0.940 0.021 1. 14555 2 194 14.8 75. 38. 92. 4.37 0.27 14555 2 195 0.947 0.025 2. 14555 2 196 14.8 75. 40. 95. 4.95 0.19 14555 2 197 1.074 0.024 3. 14555 2 198 14.8 75. 40. 97. 4.88 0.20 14555 2 199 1.057 0.028 4. 14555 2 200 14.8 75. 42. 99. 4.61 0.24 14555 2 201 5. 14555 2 202 14.8 75. 44. 103. 2.94 0.14 14555 2 203 0.636 0.015 6. 14555 2 204 14.8 75. 44. 105. 1.92 0.10 14555 2 205 0.417 0.009 7. 14555 2 206 14.8 75. 51. 127. 1.64 0.11 14555 2 207 0.355 0.008 8. 14555 2 208 14.8 75. 52. 132. 3.89 0.24 14555 2 209 0.843 0.053 10. 14555 2 210 14.8 75. 53. 131. 4.43 0.19 14555 2 211 0.959 0.034 9. 14555 2 212 14.8 75. 53. 133. 4.91 0.24 14555 2 213 1.064 0.025 11. 14555 2 214 14.8 75. 54. 135. 5.36 0.32 14555 2 215 1.162 0.071 12. 14555 2 216 14.8 75. 56. 140. 4.20 0.17 14555 2 217 0.911 0.021 14. 14555 2 218 14.8 75. 58. 143. 3.67 0.18 14555 2 219 0.796 0.041 15. 14555 2 220 14.8 75. 60. 147. 1.47 0.07 14555 2 221 0.318 0.008 16. 14555 2 222 ENDDATA 178 0 14555 2 223 ENDSUBENT 222 0 14555 299999 SUBENT 14555003 20191217 146114555 3 1 BIB 4 35 14555 3 2 REACTION 1(92-U-238(N,F)ELEM/MASS,CUM,FY) 14555 3 3 2((92-U-238(N,F)ELEM/MASS,CUM,FY)/ 14555 3 4 (92-U-238(N,F)42-MO-99,CUM,FY)) 14555 3 5 SAMPLE Enriched 238U sample with mass 441.9+-0.6 mg 14555 3 6 and diameter 12.42+-0.05 mm 14555 3 7 (92-U-238,ENR=0.99974) 14555 3 8 (92-U-235,ENR=0.00026) 14555 3 9 CORRECTION 1. Corrections to the fission chamber counts due to 14555 3 10 attenuation of the neutron flux through the various 14555 3 11 components of the dual-fission chambers: 14555 3 12 En=1.37 MeV 0.20%, 14555 3 13 En=2.37 MeV 0.24%, En=3.60 MeV 0.25%, 14555 3 14 En=4.49 MeV 0.25%, En=14.8 MeV 0.24%. 14555 3 15 The uncertainty on these corrections is on the order of14555 3 16 0.01%. 14555 3 17 2. Corrections to the fission chamber counts due to 14555 3 18 the kinematic focusing of the fission fragments emitted14555 3 19 by the monitor foil in each chamber: 14555 3 20 En=1.37 MeV 0.6%, 14555 3 21 En=2.37 MeV 0.8%, En=3.60 MeV 1.0%, 14555 3 22 En=4.49 MeV 1.1%, En=14.8 MeV 1.5%(FC1),2.0%(FC2). 14555 3 23 3. Correction factor Rg=Measured eff./Standard eff. 14555 3 24 due to errors in positioning of the activated target in14555 3 25 the counting setup for gamma-ray spectroscopy: 14555 3 26 En=1.37 MeV 0.9605, 14555 3 27 En=2.37 MeV 1.0159, En=3.60 MeV 1.0163, 14555 3 28 En=4.52 MeV 0.9895, En=14.8 MeV 0.9842. 14555 3 29 The uncertainty in R for all values about 1%. 14555 3 30 4. Corrections to the fission chamber counts due to 14555 3 31 off-energy neutrons for the 2.37 MeV data point: 14555 3 32 R=0.081, FC2 cor.=1.000, FC1 cor.=1.000. 14555 3 33 5. Corrections to the fission chamber counts due to 14555 3 34 off-energy neutrons for the 3.60 MeV data point: 14555 3 35 R=0.919, FC2 cor.=0.755+-0.002, FC1 cor.=0.780+-0.002. 14555 3 36 STATUS (TABLE) Tabs.XXI and XXIV in Nucl.Data Sh.,131,319,201614555 3 37 ENDBIB 35 0 14555 3 38 NOCOMMON 0 0 14555 3 39 DATA 9 68 14555 3 40 EN EN-RSL-FW ELEMENT MASS DATA 1ERR-T 114555 3 41 DATA 2ERR-T 2DECAY-FLAG 14555 3 42 MEV KEV NO-DIM NO-DIM PC/FIS PC/FIS 14555 3 43 NO-DIM NO-DIM NO-DIM 14555 3 44 1.37 120. 38. 91. 4.31 0.20 14555 3 45 0.718 0.016 1. 14555 3 46 1.37 120. 38. 92. 4.95 0.29 14555 3 47 0.823 0.019 2. 14555 3 48 1.37 120. 40. 97. 5.67 0.17 14555 3 49 0.944 0.015 4. 14555 3 50 1.37 120. 42. 99. 6.01 0.26 14555 3 51 5. 14555 3 52 1.37 120. 44. 105. 3.93 0.19 14555 3 53 0.655 0.018 7. 14555 3 54 1.37 120. 52. 132. 4.76 0.30 14555 3 55 0.792 0.051 10. 14555 3 56 1.37 120. 53. 131. 2.97 0.11 14555 3 57 0.495 0.018 9. 14555 3 58 1.37 120. 53. 133. 7.14 0.29 14555 3 59 1.188 0.028 11. 14555 3 60 1.37 120. 54. 135. 7.21 0.57 14555 3 61 1.200 0.102 12. 14555 3 62 1.37 120. 56. 140. 5.84 0.19 14555 3 63 0.973 0.025 14. 14555 3 64 1.37 120. 58. 143. 4.60 0.22 14555 3 65 0.765 0.043 15. 14555 3 66 1.37 120. 60. 147. 2.62 0.13 14555 3 67 0.435 0.017 16. 14555 3 68 2.37 70. 38. 91. 4.17 0.19 14555 3 69 0.645 0.010 1. 14555 3 70 2.37 70. 38. 92. 4.40 0.24 14555 3 71 0.681 0.012 2. 14555 3 72 2.37 70. 40. 95. 5.13 0.16 14555 3 73 0.795 0.012 3. 14555 3 74 2.37 70. 40. 97. 5.62 0.17 14555 3 75 0.871 0.013 4. 14555 3 76 2.37 70. 42. 99. 6.46 0.26 14555 3 77 5. 14555 3 78 2.37 70. 44. 103. 6.36 0.21 14555 3 79 0.985 0.017 6. 14555 3 80 2.37 70. 44. 105. 4.62 0.20 14555 3 81 0.715 0.012 7. 14555 3 82 2.37 70. 52. 132. 5.40 0.33 14555 3 83 0.837 0.051 10. 14555 3 84 2.37 70. 53. 131. 3.18 0.11 14555 3 85 0.492 0.016 9. 14555 3 86 2.37 70. 53. 133. 6.94 0.28 14555 3 87 1.076 0.018 11. 14555 3 88 2.37 70. 54. 135. 7.77 0.41 14555 3 89 1.203 0.071 12. 14555 3 90 2.37 70. 56. 140. 6.06 0.19 14555 3 91 0.938 0.016 14. 14555 3 92 2.37 70. 58. 143. 4.87 0.23 14555 3 93 0.755 0.037 15. 14555 3 94 2.37 70. 60. 147. 2.68 0.10 14555 3 95 0.415 0.008 16. 14555 3 96 3.60 70. 38. 91. 4.31 0.18 14555 3 97 0.653 0.013 1. 14555 3 98 3.60 70. 38. 92. 4.91 0.28 14555 3 99 0.763 0.019 2. 14555 3 100 3.60 70. 40. 95. 5.14 0.14 14555 3 101 0.799 0.015 3. 14555 3 102 3.60 70. 40. 97. 6.00 0.16 14555 3 103 0.932 0.017 4. 14555 3 104 3.60 70. 42. 99. 6.44 0.27 14555 3 105 5. 14555 3 106 3.60 70. 44. 103. 5.73 0.19 14555 3 107 0.890 0.022 6. 14555 3 108 3.60 70. 44. 105. 4.75 0.17 14555 3 109 0.735 0.015 7. 14555 3 110 3.60 70. 52. 132. 5.02 0.33 14555 3 111 0.780 0.061 10. 14555 3 112 3.60 70. 53. 131. 3.38 0.14 14555 3 113 0.525 0.029 9. 14555 3 114 3.60 70. 53. 133. 6.91 0.27 14555 3 115 1.074 0.023 11. 14555 3 116 3.60 70. 54. 135. 6.38 0.38 14555 3 117 0.992 0.082 12. 14555 3 118 3.60 70. 56. 140. 5.84 0.17 14555 3 119 0.907 0.019 14. 14555 3 120 3.60 70. 58. 143. 4.51 0.22 14555 3 121 0.700 0.055 15. 14555 3 122 3.60 70. 60. 147. 2.81 0.10 14555 3 123 0.436 0.010 16. 14555 3 124 4.49 250. 38. 91. 3.95 0.18 14555 3 125 0.602 0.012 1. 14555 3 126 4.49 250. 38. 92. 4.13 0.25 14555 3 127 0.629 0.016 2. 14555 3 128 4.49 250. 40. 95. 5.26 0.17 14555 3 129 0.802 0.015 3. 14555 3 130 4.49 250. 40. 97. 5.83 0.18 14555 3 131 0.888 0.016 4. 14555 3 132 4.49 250. 42. 99. 6.56 0.29 14555 3 133 5. 14555 3 134 4.49 250. 44. 103. 5.73 0.21 14555 3 135 0.873 0.021 6. 14555 3 136 4.49 250. 44. 105. 4.65 0.17 14555 3 137 0.709 0.015 7. 14555 3 138 4.49 250. 52. 132. 5.03 0.29 14555 3 139 0.767 0.060 10. 14555 3 140 4.49 250. 53. 131. 3.38 0.15 14555 3 141 0.516 0.029 9. 14555 3 142 4.49 250. 53. 133. 6.70 0.28 14555 3 143 1.021 0.022 11. 14555 3 144 4.49 250. 54. 135. 6.52 0.38 14555 3 145 0.994 0.082 12. 14555 3 146 4.49 250. 56. 140. 5.78 0.20 14555 3 147 0.882 0.019 14. 14555 3 148 4.49 250. 58. 143. 4.71 0.24 14555 3 149 0.718 0.056 15. 14555 3 150 4.49 250. 60. 147. 2.66 0.11 14555 3 151 0.406 0.011 16. 14555 3 152 14.8 75. 38. 91. 3.65 0.16 14555 3 153 0.645 0.010 1. 14555 3 154 14.8 75. 38. 92. 3.82 0.21 14555 3 155 0.674 0.012 2. 14555 3 156 14.8 75. 40. 95. 4.87 0.14 14555 3 157 0.859 0.013 3. 14555 3 158 14.8 75. 40. 97. 4.97 0.14 14555 3 159 0.877 0.013 4. 14555 3 160 14.8 75. 42. 99. 5.66 0.22 14555 3 161 5. 14555 3 162 14.8 75. 44. 103. 4.72 0.15 14555 3 163 0.834 0.015 6. 14555 3 164 14.8 75. 44. 105. 3.26 0.10 14555 3 165 0.560 0.008 7. 14555 3 166 14.8 75. 52. 132. 4.96 0.28 14555 3 167 0.875 0.054 10. 14555 3 168 14.8 75. 53. 131. 3.94 0.14 14555 3 169 0.696 0.022 9. 14555 3 170 14.8 75. 53. 133. 5.83 0.23 14555 3 171 1.029 0.017 11. 14555 3 172 14.8 75. 54. 135. 5.74 0.30 14555 3 173 1.013 0.060 12. 14555 3 174 14.8 75. 56. 140. 4.69 0.14 14555 3 175 0.828 0.013 14. 14555 3 176 14.8 75. 58. 143. 4.02 0.16 14555 3 177 0.710 0.034 15. 14555 3 178 14.8 75. 60. 147. 2.10 0.07 14555 3 179 0.371 0.006 16. 14555 3 180 ENDDATA 140 0 14555 3 181 ENDSUBENT 180 0 14555 399999 SUBENT 14555004 20191217 146114555 4 1 BIB 4 39 14555 4 2 REACTION 1(94-PU-239(N,F)ELEM/MASS,CUM,FY) 14555 4 3 2((94-PU-239(N,F)ELEM/MASS,CUM,FY)/ 14555 4 4 (94-PU-239(N,F)42-MO-99,CUM,FY)) 14555 4 5 SAMPLE Enriched 239PU samples: with mass 233.0+-0.2 mg 14555 4 6 and diameter 12.39+-0.05 mm (#3), with mass 14555 4 7 233.7+-0.2 mg and diameter 12.40+-0.05 mm (#8). 14555 4 8 (94-PU-239,ENR=0.9841) 14555 4 9 (94-PU-240,ENR=0.0158) 14555 4 10 (94-PU-241,ENR=0.00003) 14555 4 11 (94-PU-242,ENR=0.00003) 14555 4 12 CORRECTION 1. Corrections to the fission chamber counts due to 14555 4 13 attenuation of the neutron flux through the various 14555 4 14 components of the dual-fission chambers: 14555 4 15 En=0.56 MeV 0.08%, En=1.37 MeV 0.24%, 14555 4 16 En=2.37 MeV 0.29%, En=3.60 MeV 0.34%, 14555 4 17 En=4.49 MeV 0.33%, En=5.5 MeV 0.33%, 14555 4 18 En=14.8 MeV 0.34%. The uncertainty on these 14555 4 19 corrections is on the order of 0.01%. 14555 4 20 2. Corrections to the fission chamber counts due to 14555 4 21 the kinematic focusing of the fission fragments emitted14555 4 22 by the monitor foil in each chamber: 14555 4 23 En=0.56 MeV 0.4%, En=1.37 MeV 0.6%, 14555 4 24 En=2.37 MeV 0.8%, En=3.60 MeV 1.0%, 14555 4 25 En=4.49 MeV 1.1%, En=5.5 MeV 1.1%, 14555 4 26 En=14.8 MeV 1.5%(FC1),2.0%(FC2). 14555 4 27 3. Correction factor Rg=Measured eff./Standard eff. 14555 4 28 due to errors in positioning of the activated target in14555 4 29 the counting setup for gamma-ray spectroscopy: 14555 4 30 En=0.58 MeV 0.9926, En=1.37 MeV 0.9938, 14555 4 31 En=2.37 MeV 1.0089, En=3.60 MeV 1.0166, 14555 4 32 En=4.52 MeV 1.0052, En=14.8 MeV 1.0199. 14555 4 33 The uncertainty in R for all values about 1%. 14555 4 34 4. Corrections to the fission chamber counts due to 14555 4 35 off-energy neutrons for the 2.37 MeV data point: 14555 4 36 R=1.007, FC2 cor.=0.964+-0.002, FC1 cor.=0.961+-0.002. 14555 4 37 5. Corrections to the fission chamber counts due to 14555 4 38 off-energy neutrons for the 3.60 MeV data point: 14555 4 39 R=0.986, FC2 cor.=0.758+-0.002, FC1 cor.=0.764+-0.002. 14555 4 40 STATUS (TABLE) Tabs.XXII and XXV in Nucl.Data Sh.,131,319,201614555 4 41 ENDBIB 39 0 14555 4 42 NOCOMMON 0 0 14555 4 43 DATA 9 98 14555 4 44 EN EN-RSL-FW ELEMENT MASS DATA 1ERR-T 114555 4 45 DATA 2ERR-T 2DECAY-FLAG 14555 4 46 MEV KEV NO-DIM NO-DIM PC/FIS PC/FIS 14555 4 47 NO-DIM NO-DIM NO-DIM 14555 4 48 0.58 30. 38. 91. 2.78 0.13 14555 4 49 0.410 0.008 1. 14555 4 50 0.58 30. 38. 92. 3.16 0.18 14555 4 51 0.465 0.010 2. 14555 4 52 0.58 30. 40. 95. 4.87 0.15 14555 4 53 0.717 0.011 3. 14555 4 54 0.58 30. 40. 97. 5.47 0.17 14555 4 55 0.806 0.013 4. 14555 4 56 0.58 30. 42. 99. 6.79 0.31 14555 4 57 5. 14555 4 58 0.58 30. 44. 103. 6.68 0.23 14555 4 59 0.984 0.018 6. 14555 4 60 0.58 30. 44. 105. 5.79 0.20 14555 4 61 0.867 0.015 7. 14555 4 62 0.58 30. 51. 127. 0.48 0.03 14555 4 63 0.070 0.002 8. 14555 4 64 0.58 30. 52. 132. 5.11 0.26 14555 4 65 0.753 0.026 10. 14555 4 66 0.58 30. 53. 133. 6.84 0.28 14555 4 67 1.008 0.017 11. 14555 4 68 0.58 30. 54. 135. 7.56 0.36 14555 4 69 1.113 0.034 12. 14555 4 70 0.58 30. 56. 140. 5.49 0.20 14555 4 71 0.809 0.021 14. 14555 4 72 0.58 30. 58. 143. 4.38 0.16 14555 4 73 0.646 0.020 15. 14555 4 74 0.58 30. 60. 147. 2.01 0.08 14555 4 75 0.296 0.007 16. 14555 4 76 1.37 120. 38. 91. 2.89 0.13 14555 4 77 0.416 0.07 1. 14555 4 78 1.37 120. 38. 92. 3.21 0.18 14555 4 79 0.461 0.010 2. 14555 4 80 1.37 120. 40. 95. 5.05 0.16 14555 4 81 0.726 0.011 3. 14555 4 82 1.37 120. 40. 97. 5.56 0.17 14555 4 83 0.799 0.012 4. 14555 4 84 1.37 120. 42. 99. 6.95 0.32 14555 4 85 5. 14555 4 86 1.37 120. 44. 103. 6.73 0.23 14555 4 87 0.968 0.017 6. 14555 4 88 1.37 120. 44. 105. 5.61 0.19 14555 4 89 0.834 0.013 7. 14555 4 90 1.37 120. 51. 127. 0.53 0.03 14555 4 91 0.077 0.001 8. 14555 4 92 1.37 120. 52. 132. 5.41 0.27 14555 4 93 0.779 0.025 10. 14555 4 94 1.37 120. 53. 133. 6.93 0.28 14555 4 95 0.997 0.017 11. 14555 4 96 1.37 120. 54. 135. 7.77 0.37 14555 4 97 1.118 0.034 12. 14555 4 98 1.37 120. 56. 140. 5.38 0.17 14555 4 99 0.774 0.013 14. 14555 4 100 1.37 120. 58. 143. 4.46 0.16 14555 4 101 0.642 0.021 15. 14555 4 102 1.37 120. 60. 147. 2.13 0.09 14555 4 103 0.307 0.009 16. 14555 4 104 2.37 70. 38. 91. 3.19 0.15 14555 4 105 0.449 0.008 1. 14555 4 106 2.37 70. 38. 92. 3.41 0.20 14555 4 107 0.480 0.010 2. 14555 4 108 2.37 70. 40. 95. 5.41 0.17 14555 4 109 0.761 0.012 3. 14555 4 110 2.37 70. 40. 97. 5.93 0.18 14555 4 111 0.834 0.013 4. 14555 4 112 2.37 70. 42. 99. 7.11 0.33 14555 4 113 5. 14555 4 114 2.37 70. 44. 103. 6.90 0.24 14555 4 115 0.971 0.018 6. 14555 4 116 2.37 70. 44. 105. 5.51 0.19 14555 4 117 0.799 0.014 7. 14555 4 118 2.37 70. 51. 127. 0.73 0.05 14555 4 119 0.103 0.002 8. 14555 4 120 2.37 70. 52. 132. 5.48 0.28 14555 4 121 0.771 0.027 10. 14555 4 122 2.37 70. 53. 133. 7.20 0.30 14555 4 123 1.012 0.018 11. 14555 4 124 2.37 70. 54. 135. 8.44 0.41 14555 4 125 1.187 0.036 12. 14555 4 126 2.37 70. 56. 140. 5.52 0.18 14555 4 127 0.776 0.014 14. 14555 4 128 2.37 70. 58. 143. 4.48 0.17 14555 4 129 0.630 0.021 15. 14555 4 130 2.37 70. 60. 147. 2.29 0.11 14555 4 131 0.322 0.011 16. 14555 4 132 3.60 70. 38. 91. 3.16 0.14 14555 4 133 0.461 0.008 1. 14555 4 134 3.60 70. 38. 92. 3.30 0.18 14555 4 135 0.481 0.010 2. 14555 4 136 3.60 70. 40. 95. 5.43 0.15 14555 4 137 0.790 0.012 3. 14555 4 138 3.60 70. 40. 97. 5.90 0.15 14555 4 139 0.859 0.013 4. 14555 4 140 3.60 70. 42. 99. 6.87 0.33 14555 4 141 5. 14555 4 142 3.60 70. 44. 103. 6.90 0.22 14555 4 143 1.004 0.021 6. 14555 4 144 3.60 70. 44. 105. 5.51 0.16 14555 4 145 0.799 0.013 7. 14555 4 146 3.60 70. 51. 127. 0.92 0.02 14555 4 147 0.133 0.003 8. 14555 4 148 3.60 70. 52. 132. 5.42 0.27 14555 4 149 0.789 0.035 10. 14555 4 150 3.60 70. 53. 133. 7.14 0.27 14555 4 151 1.040 0.019 11. 14555 4 152 3.60 70. 54. 135. 8.01 0.40 14555 4 153 1.166 0.055 12. 14555 4 154 3.60 70. 56. 140. 5.52 0.16 14555 4 155 0.804 0.015 14. 14555 4 156 3.60 70. 58. 143. 4.58 0.18 14555 4 157 0.666 0.033 15. 14555 4 158 3.60 70. 60. 147. 2.39 0.10 14555 4 159 0.347 0.010 16. 14555 4 160 4.49 250. 38. 91. 3.08 0.14 14555 4 161 0.457 0.008 1. 14555 4 162 4.49 250. 38. 92. 3.25 0.19 14555 4 163 0.483 0.011 2. 14555 4 164 4.49 250. 40. 95. 5.21 0.16 14555 4 165 0.774 0.013 3. 14555 4 166 4.49 250. 40. 97. 5.77 0.18 14555 4 167 0.857 0.014 4. 14555 4 168 4.49 250. 42. 99. 6.73 0.29 14555 4 169 5. 14555 4 170 4.49 250. 44. 103. 6.55 0.23 14555 4 171 0.973 0.020 6. 14555 4 172 4.49 250. 44. 105. 5.29 0.21 14555 4 173 0.808 0.020 7. 14555 4 174 4.49 250. 51. 127. 1.17 0.06 14555 4 175 0.175 0.006 8. 14555 4 176 4.49 250. 52. 132. 5.23 0.27 14555 4 177 0.777 0.034 10. 14555 4 178 4.49 250. 53. 133. 6.60 0.27 14555 4 179 0.981 0.019 11. 14555 4 180 4.49 250. 54. 135. 7.28 0.38 14555 4 181 1.082 0.051 12. 14555 4 182 4.49 250. 56. 140. 5.23 0.19 14555 4 183 0.777 0.020 14. 14555 4 184 4.49 250. 58. 143. 4.34 0.22 14555 4 185 0.645 0.036 15. 14555 4 186 4.49 250. 60. 147. 2.34 0.10 14555 4 187 0.348 0.010 16. 14555 4 188 5.50 140. 38. 91. 3.12 0.13 14555 4 189 0.470 0.015 1. 14555 4 190 5.50 140. 38. 92. 3.18 0.22 14555 4 191 0.480 0.019 2. 14555 4 192 5.50 140. 40. 95. 5.25 0.15 14555 4 193 0.792 0.016 3. 14555 4 194 5.50 140. 40. 97. 5.83 0.17 14555 4 195 0.880 0.019 4. 14555 4 196 5.50 140. 42. 99. 6.63 0.29 14555 4 197 5. 14555 4 198 5.50 140. 44. 103. 6.37 0.19 14555 4 199 0.961 0.019 6. 14555 4 200 5.50 140. 44. 105. 5.43 0.16 14555 4 201 0.853 0.018 7. 14555 4 202 5.50 140. 51. 127. 1.33 0.04 14555 4 203 0.201 0.004 8. 14555 4 204 5.50 140. 52. 132. 4.90 0.23 14555 4 205 0.739 0.024 10. 14555 4 206 5.50 140. 53. 133. 6.59 0.25 14555 4 207 0.994 0.020 11. 14555 4 208 5.50 140. 54. 135. 7.30 0.34 14555 4 209 1.101 0.037 12. 14555 4 210 5.50 140. 56. 140. 5.07 0.15 14555 4 211 0.766 0.016 14. 14555 4 212 5.50 140. 58. 143. 4.06 0.15 14555 4 213 0.613 0.021 15. 14555 4 214 5.50 140. 60. 147. 2.33 0.11 14555 4 215 0.351 0.013 16. 14555 4 216 14.8 75. 38. 91. 2.62 0.12 14555 4 217 0.505 0.020 1. 14555 4 218 14.8 75. 38. 92. 2.66 0.16 14555 4 219 0.491 0.014 2. 14555 4 220 14.8 75. 40. 95. 4.32 0.14 14555 4 221 0.796 0.018 3. 14555 4 222 14.8 75. 40. 97. 4.74 0.17 14555 4 223 0.875 0.025 4. 14555 4 224 14.8 75. 42. 99. 5.42 0.26 14555 4 225 5. 14555 4 226 14.8 75. 44. 103. 5.38 0.19 14555 4 227 0.991 0.026 6. 14555 4 228 14.8 75. 44. 105. 4.23 0.17 14555 4 229 0.787 0.020 7. 14555 4 230 14.8 75. 51. 127. 2.27 0.14 14555 4 231 0.419 0.010 8. 14555 4 232 14.8 75. 52. 132. 3.18 0.18 14555 4 233 0.586 0.029 10. 14555 4 234 14.8 75. 53. 133. 4.69 0.20 14555 4 235 0.863 0.021 11. 14555 4 236 14.8 75. 54. 135. 5.27 0.28 14555 4 237 0.972 0.049 12. 14555 4 238 14.8 75. 56. 140. 3.95 0.17 14555 4 239 0.729 0.025 14. 14555 4 240 14.8 75. 58. 143. 2.90 0.14 14555 4 241 0.534 0.029 15. 14555 4 242 14.8 75. 60. 147. 1.67 0.08 14555 4 243 0.308 0.011 16. 14555 4 244 ENDDATA 200 0 14555 4 245 ENDSUBENT 244 0 14555 499999 SUBENT 14555005 20191217 146114555 5 1 BIB 5 40 14555 5 2 REACTION 1(94-PU-239(N,F)55-CS-136,IND,FY) 14555 5 3 2((94-PU-239(N,F)55-CS-136,IND,FY)/ 14555 5 4 (94-PU-239(N,F)42-MO-99,CUM,FY)) 14555 5 5 SAMPLE Enriched 239PU samples: with mass 233.0+-0.2 mg 14555 5 6 and diameter 12.39+-0.05 mm (#3), with mass 14555 5 7 233.7+-0.2 mg and diameter 12.40+-0.05 mm (#8). 14555 5 8 (94-PU-239,ENR=0.9841) 14555 5 9 (94-PU-240,ENR=0.0158) 14555 5 10 (94-PU-241,ENR=0.00003) 14555 5 11 (94-PU-242,ENR=0.00003) 14555 5 12 DECAY-DATA (55-CS-136-G,13.16D,DG,1048.07,0.80) 14555 5 13 CORRECTION 1. Corrections to the fission chamber counts due to 14555 5 14 attenuation of the neutron flux through the various 14555 5 15 components of the dual-fission chambers: 14555 5 16 En=0.56 MeV 0.08%, En=1.37 MeV 0.24%, 14555 5 17 En=2.37 MeV 0.29%, En=3.60 MeV 0.34%, 14555 5 18 En=4.49 MeV 0.33%, En=5.5 MeV 0.33%, 14555 5 19 En=14.8 MeV 0.34%. The uncertainty on these 14555 5 20 corrections is on the order of 0.01%. 14555 5 21 2. Corrections to the fission chamber counts due to 14555 5 22 the kinematic focusing of the fission fragments emitted14555 5 23 by the monitor foil in each chamber: 14555 5 24 En=0.56 MeV 0.4%, En=1.37 MeV 0.6%, 14555 5 25 En=2.37 MeV 0.8%, En=3.60 MeV 1.0%, 14555 5 26 En=4.49 MeV 1.1%, En=5.5 MeV 1.1%, 14555 5 27 En=14.8 MeV 1.5%(FC1),2.0%(FC2). 14555 5 28 3. Correction factor Rg=Measured eff./Standard eff. 14555 5 29 due to errors in positioning of the activated target in14555 5 30 the counting setup for gamma-ray spectroscopy: 14555 5 31 En=0.58 MeV 0.9926, En=1.37 MeV 0.9938, 14555 5 32 En=2.37 MeV 1.0089, En=3.60 MeV 1.0166, 14555 5 33 En=4.52 MeV 1.0052, En=14.8 MeV 1.0199. 14555 5 34 The uncertainty in R for all values about 1%. 14555 5 35 4. Corrections to the fission chamber counts due to 14555 5 36 off-energy neutrons for the 2.37 MeV data point: 14555 5 37 R=1.007, FC2 cor.=0.964+-0.002, FC1 cor.=0.961+-0.002. 14555 5 38 5. Corrections to the fission chamber counts due to 14555 5 39 off-energy neutrons for the 3.60 MeV data point: 14555 5 40 R=0.986, FC2 cor.=0.758+-0.002, FC1 cor.=0.764+-0.002. 14555 5 41 STATUS (TABLE) Tabs.XXII and XXV in Nucl.Data Sh.,131,319,201614555 5 42 ENDBIB 40 0 14555 5 43 COMMON 2 3 14555 5 44 ELEMENT MASS 14555 5 45 NO-DIM NO-DIM 14555 5 46 55. 136. 14555 5 47 ENDCOMMON 3 0 14555 5 48 DATA 6 7 14555 5 49 EN EN-RSL-FW DATA 1ERR-T 1DATA 2ERR-T 214555 5 50 MEV KEV PC/FIS PC/FIS NO-DIM NO-DIM 14555 5 51 0.58 30. 0.087 0.005 0.013 0.001 14555 5 52 1.37 120. 0.13 0.01 0.018 0.001 14555 5 53 2.37 70. 0.16 0.01 0.024 0.001 14555 5 54 3.60 70. 0.24 0.01 0.035 0.001 14555 5 55 4.49 250. 0.31 0.02 0.046 0.001 14555 5 56 5.50 140. 0.35 0.02 0.053 0.001 14555 5 57 14.8 75. 0.82 0.04 0.152 0.004 14555 5 58 ENDDATA 9 0 14555 5 59 ENDSUBENT 58 0 14555 599999 ENDENTRY 5 0 1455599999999