ENTRY 14555 20250601 152014555000 1 SUBENT 14555001 20250601 152014555001 1 BIB 14 154 14555001 2 TITLE Energy dependence of fission product yields from 235U, 14555001 3 238U and 239Pu for incident neutron energies between 14555001 4 0.5 and 14.8 MeV 14555001 5 AUTHOR (M.E.Gooden,C.W.Arnold,J.A.Becker,C.Bhatia,M.Bhike, 14555001 6 E.M.Bond, T.A.Bredeweg,B.Fallin,M.M.Fowler,C.R.Howell, 14555001 7 J.H.Kelley, Krishichayan,R.Macri,G.Rusev,C.Ryan, 14555001 8 S.A.Sheets,M.A.Stoyer, A.P.Tonchev,W.Tornow, 14555001 9 D.J.Vieira,J.B.Wilhelmy) 14555001 10 INSTITUTE (1USALAS,1USALRL,1CANMCM,1USADKE,1USATNL,1USANCS) 14555001 11 REFERENCE (J,NDS,131,319,2016) 14555001 12 #doi:10.1016/j.nds.2015.12.006 14555001 13 #NSR: 2016GO02 14555001 14 (J,NDS,119,324,2014) Prelim. data for 4.6,9.0,14.5 MeV.14555001 15 #doi:10.1016/j.nds.2014.08.089 14555001 16 #NSR: 2014BH11 14555001 17 (J,EPJ/CS,146,04024,2017) Cumulative fission product 14555001 18 yields for 147Nd (presented in figs.) 14555001 19 #doi:10.1051/epjconf/201714604024 14555001 20 #NSR: 2017GOZW 14555001 21 #doi:10.1103/PhysRevC.91.064604 14555001 22 #NSR: 2015BH09 14555001 23 REL-REF (O,14423001,C.Bhatia+,J,PR/C,91,064604,2015) Data for 14555001 24 8.9 MeV included in Entry 14423. 14555001 25 FACILITY (VDGT,1USATNL) Experiments performed at the Triangle 14555001 26 Universities Nuclear Laboratory on the campus of Duke 14555001 27 University using a 10 MV FN Tandem Van de Graaff 14555001 28 accelerator. 14555001 29 DETECTOR (FISCH) Each measurement used a single dual-fission 14555001 30 chamber placed in close proximity to the neutron 14555001 31 production source. A special mounting was created to 14555001 32 allow fine adjustments of the position of the fission 14555001 33 chamber relative to the end of the beam line. Using a 14555001 34 fixed spacer, 15.8 mm wide, the fission chambers were 14555001 35 set a fixed distance from the end of the beam line. 14555001 36 Finally, a fixed telescope downstream at 0 degree, 14555001 37 was used to adjust the horizontal and vertical 14555001 38 positioning of the chamber so that it was centered on 14555001 39 the same position as the neutron production source. 14555001 40 This enabled reproducible positioning of the fission 14555001 41 chambers between different measurements. Since 235U 14555001 42 and 239Pu have substantial thermal cross sections, a 14555001 43 cadmium cover(hat) was made that fit over the top of 14555001 44 the fission chambers. The Cd-hat reduces the 14555001 45 room-return neutrons by approximately a factor of 2. 14555001 46 A BC-501A liquid scintillator neutron detector was also14555001 47 placed about 3 m downstream from the neutron 14555001 48 production source which served as flux monitor and was 14555001 49 used during neutron time-of-flight measurements. 14555001 50 A single dual-fission chamber (DFC) contains a thick 14555001 51 activation target and two thin reference foils of the 14555001 52 same isotope. The body of each DFC has an outer 14555001 53 diameter of 2.50 cm and an overall thickness of 14555001 54 1.73 cm. The total volume of the DFC is about 3.5 cm3. 14555001 55 The efficiency of the FCs were determined by preparing 14555001 56 252Cf sources in the same configuration as the 14555001 57 reference foils. The fission detection efficiency was 14555001 58 98.5%. 14555001 59 (HPGE) Gamma rays from fission products were measured 14555001 60 using lead-shielded High-Purity Germanium detectors 14555001 61 over a period of 1.5-2 months after activation using 14555001 62 a number of different counting cycles. 14555001 63 METHOD (ACTIV) Fission yields were determined by activation 14555001 64 method using characteristic gamma rays of fission 14555001 65 products. 14555001 66 INC-SOURCE (P-LI7) The 7Li(p,n) 7Be reaction was used to achieve 14555001 67 about 0.5 MeV neutrons. For incident proton energies 14555001 68 greater than 2.372 MeV, the 7Li(p,n)7Be reaction is no 14555001 69 longer monoenergetic, due to the opening of the neutron14555001 70 emission channel from the first excited state of 7Be 14555001 71 at 429 keV. Neutron production targets for this 14555001 72 reaction were produced by evaporation of lithium 14555001 73 fluoride (LiF) powder onto 19 mm diameter by 0.2 mm 14555001 74 thick aluminum disks. The mass of the LiF varied 14555001 75 between 0.9 and 1.2 mg between the various targets that14555001 76 were produced. The mean incident neutron energy 14555001 77 achieved on target using this reaction was 0.56 MeV 14555001 78 with a total spread in neutron energy of +-30 keV. 14555001 79 (P-T) The 3H(p,n) 3He reaction produces monoenergetic 14555001 80 neutrons up to incident proton energies of 8.348 MeV, 14555001 81 resulting in a maximum neutron energy of 7.7 MeV. For 14555001 82 these measurements, this reaction was used to produce 14555001 83 neutrons at about 1.37, 2.37 and 3.60 MeV, with total 14555001 84 energy spreads of +-120, 70 and 70 keV respectively. 14555001 85 The tritiated target consists of a 19 mm diameter by 14555001 86 0.4 mm thick Cu disk on which a 16 mm diameter and 14555001 87 2.2 mg/cm2 thick layer of titanium was evaporated. 14555001 88 Into the Ti layer 2.1 Ci of tritium was absorbed, 14555001 89 giving a ratio of T/Ti >1.5. In order to provide 14555001 90 cooling to the Havar foil and tritiated target, a 14555001 91 helium gas buffer cell (usually pressurized to about 14555001 92 1.5 atm) is used upstream from the production target 14555001 93 foil. The Cu disk and the copper target chamber are 14555001 94 cooled from the outside with separate gas lines of 14555001 95 both compressed and chilled air. For proton beam 14555001 96 currents between 2 and 4 mu-A, a water cooled target 14555001 97 chamber made of copper was used in place of the 14555001 98 stainless steel target chamber. 14555001 99 (D-D) The reaction 2H(d,n) 3He was used to produce 14555001 100 neutrons with energies of 4.56, 5.5 and 8.9 MeV. The 14555001 101 measurements at these energies had spreads (FWHM) in 14555001 102 the neutron energy of +-250, 140 and 100 keV, 14555001 103 respectively. 14555001 104 (D-T) The 3H(d,n) 4He reaction was used to produce 14555001 105 neutrons at the nearby energy of 14.8 MeV with an 14555001 106 energy spread of +-75 keV. 14555001 107 DECAY-DATA ((1.)38-SR-91,9.63HR,DG,1024.3,0.335) 14555001 108 ((2.)38-SR-92,2.611HR,DG,1383.93,0.90) 14555001 109 ((3.)40-ZR-95,64.032D,DG,724.192,0.4427) 14555001 110 ((4.)40-ZR-97,16.749HR,DG,743.36,0.9309) 14555001 111 ((5.)42-MO-99,65.976HR,DG,739.500,0.1226) 14555001 112 ((6.)44-RU-103,39.247D,DG,497.09,0.910) 14555001 113 ((7.)44-RU-105,4.44HR,DG,724.30,0.473) 14555001 114 ((8.)51-SB-127,3.85D,DG,685.7,0.368) 14555001 115 ((9.)53-I-131,8.0252D,DG,364.489,0.815) 14555001 116 ((10.)52-TE-132,3.204D,DG,228.16,0.88) 14555001 117 ((11.)53-I-133-G,20.83HR,DG,529.872,0.870) 14555001 118 ((12.)54-XE-135-G,9.14HR,DG,249.794,0.90) 14555001 119 ((14.)56-BA-140,12.7527D,DG,537.261,0.2439) 14555001 120 ((15.)58-CE-143,33.039HR,DG,293.266,0.428) 14555001 121 ((16.)60-ND-147,10.98D,DG,531.016,0.1337) 14555001 122 ERR-ANALYS The following partial uncertainties are not included in14555001 123 the total uncertainty (<1% for each): 14555001 124 half-life, counting time, decay time, irradiation time14555001 125 room-return neutron backgrounds. 14555001 126 (ERR-T) The total uncertainty is determined by summing 14555001 127 in quadrature the different components listed below. 14555001 128 (ERR-1,0.2,6.) photo-peak area 14555001 129 (ERR-2,0.01,0.5) neutron flux correction 14555001 130 1(ERR-3,2.,5.) HPGe efficiency 14555001 131 (ERR-4) fission chamber efficiency (1.5%) 14555001 132 (ERR-5,0.1,5.4) gamma-ray emission probability 14555001 133 (ERR-6) target positioning correction (~1%) 14555001 134 (ERR-7) gamma-ray absorption (1.06%) 14555001 135 (ERR-8,0.01,0.04) target mass 14555001 136 (ERR-9,2.,4.) coincidence summing 14555001 137 (ERR-10,0.,2.) neutron backgrounds (off-energy) 14555001 138 2(ERR-3,0.1,0.2) efficiency ratio 14555001 139 (ERR-4) gamma-ray absorption (0.2%) 14555001 140 CORRECTION Data were corrected for 14555001 141 1) Dead time correction (1%). 14555001 142 2) The photon self-attenuation correction for each 14555001 143 identified fission product for each target at the far 14555001 144 (5 cm) counting position. 14555001 145 3) An average correction for fluctuations in the 14555001 146 neutron flux during irradiation for each fission 14555001 147 product. 14555001 148 COMMENT In the text in Nucl.Data Sh.,131,319,2016 on p.322 14555001 149 for 7Li(p,n)7Be reaction: 'The mean incident neutron 14555001 150 energy achieved on target using this reaction was 14555001 151 0.56 MeV and marks the lowest energy data point in this14555001 152 set of measurements'. In the tables this energy is 14555001 153 equal 0.58 MeV. This value was used by compiler. 14555001 154 HISTORY (20191210C) OG. 14555001 155 (20250425A) OS. Corrections in data table in sub.2 14555001 156 ENDBIB 154 0 14555001 157 COMMON 4 3 14555001 158 ERR-4 1ERR-6 1ERR-7 1ERR-4 2 14555001 159 PER-CENT PER-CENT PER-CENT PER-CENT 14555001 160 1.5 1. 1.06 0.2 14555001 161 ENDCOMMON 3 0 14555001 162 ENDSUBENT 161 0 1455500199999 SUBENT 14555002 20250601 152014555002 1 BIB 5 43 14555002 2 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY) 14555002 3 2((92-U-235(N,F)ELEM/MASS,CUM,FY)/ 14555002 4 (92-U-235(N,F)42-MO-99,CUM,FY)) 14555002 5 SAMPLE Enriched 235U sample with mass 233.02+-0.02 mg 14555002 6 and diameter 12.35+-0.05 mm 14555002 7 (92-U-235,ENR=0.9327) 14555002 8 (92-U-234,ENR=0.0105) 14555002 9 (92-U-238,ENR=0.0568) 14555002 10 CORRECTION 1. Corrections to the fission chamber counts due to 14555002 11 attenuation of the neutron flux through the various 14555002 12 components of the dual-fission chambers: 14555002 13 En=0.56 MeV 0.07%, En=1.37 MeV 0.13%, 14555002 14 En=2.37 MeV 0.16%, En=3.60 MeV 0.19%, 14555002 15 En=4.49 MeV 0.18%, En=14.8 MeV 0.18%. 14555002 16 The uncertainty on these corrections is on the order of14555002 17 0.01%. 14555002 18 2. Corrections to the fission chamber counts due to 14555002 19 the kinematic focusing of the fission fragments emitted14555002 20 by the monitor foil in each chamber: 14555002 21 En=0.56 MeV 0.4%, En=1.37 MeV 0.6%, 14555002 22 En=2.37 MeV 0.8%, En=3.60 MeV 1.0%, 14555002 23 En=4.49 MeV 1.1%, En=14.8 MeV 1.5%(FC1),2.0%(FC2). 14555002 24 3. Correction factor Rg=Measured eff./Standard eff. 14555002 25 due to errors in positioning of the activated target in14555002 26 the counting setup for gamma-ray spectroscopy: 14555002 27 En=0.58 MeV 1.0307, En=1.37 MeV 1.0096, 14555002 28 En=2.37 MeV 1.0307, En=3.60 MeV 1.0163, 14555002 29 En=4.52 MeV 1.0343, En=14.8 MeV 1.0230. 14555002 30 The uncertainty in R for all values about 1%. 14555002 31 4. Corrections to the fission chamber counts due to 14555002 32 off-energy neutrons for the 2.37 MeV data point: 14555002 33 R=1.000, FC2 cor.=0.964+-0.002, FC1 cor.=0.961+-0.002. 14555002 34 5. Corrections to the fission chamber counts due to 14555002 35 off-energy neutrons for the 3.60 MeV data point: 14555002 36 R=1.000, FC2 cor.=0.755+-0.002, FC1 cor.=0.761+-0.002. 14555002 37 6. The isotopic corrections to the 235U fission 14555002 38 product yields due to the 238U isotopic contribution in14555002 39 the target. 14555002 40 STATUS (TABLE,,M.E.Gooden+,J,NDS,131,319,2016) 14555002 41 Tabs.XX and XXIII in Nucl.Data Sh.,131,319,2016 14555002 42 HISTORY (20250425A) DATA 2: Several data corrections at 14555002 43 4.49 MeV, and some deletions for erroneous data points14555002 44 for Mo-99 14555002 45 ENDBIB 43 0 14555002 46 NOCOMMON 0 0 14555002 47 DATA 9 87 14555002 48 EN EN-RSL-FW ELEMENT MASS DATA 1ERR-T 114555002 49 DATA 2ERR-T 2DECAY-FLAG 14555002 50 MEV KEV NO-DIM NO-DIM PC/FIS PC/FIS 14555002 51 NO-DIM NO-DIM NO-DIM 14555002 52 0.58 30. 38. 91. 5.83 0.26 14555002 53 0.985 0.016 1. 14555002 54 0.58 30. 38. 92. 5.96 0.34 14555002 55 1.007 0.020 2. 14555002 56 0.58 30. 40. 95. 6.22 0.25 14555002 57 1.051 0.024 3. 14555002 58 0.58 30. 40. 97. 6.05 0.18 14555002 59 1.022 0.016 4. 14555002 60 0.58 30. 42. 99. 5.92 0.24 14555002 61 5. 14555002 62 0.58 30. 44. 103. 3.18 0.11 14555002 63 0.537 0.010 6. 14555002 64 0.58 30. 44. 105. 1.06 0.08 14555002 65 0.179 0.005 7. 14555002 66 0.58 30. 51. 127. 0.20 0.01 14555002 67 0.033 0.001 8. 14555002 68 0.58 30. 52. 132. 4.8 0.26 14555002 69 0.811 0.050 10. 14555002 70 0.58 30. 53. 131. 3.12 0.11 14555002 71 0.527 0.017 9. 14555002 72 0.58 30. 53. 133. 6.97 0.28 14555002 73 1.178 0.020 11. 14555002 74 0.58 30. 54. 135. 7.01 0.38 14555002 75 1.184 0.070 12. 14555002 76 0.58 30. 56. 140. 5.78 0.19 14555002 77 0.976 0.017 14. 14555002 78 0.58 30. 58. 143. 5.84 0.24 14555002 79 0.986 0.048 15. 14555002 80 0.58 30. 60. 147. 2.16 0.09 14555002 81 0.364 0.009 16. 14555002 82 1.37 120. 38. 91. 4.99 0.22 14555002 83 0.865 0.016 1. 14555002 84 1.37 120. 38. 92. 5.19 0.30 14555002 85 0.900 0.023 2. 14555002 86 1.37 120. 40. 97. 5.65 0.016 14555002 87 0.979 0.016 4. 14555002 88 1.37 120. 42. 99. 5.77 0.023 14555002 89 5. 14555002 90 1.37 120. 44. 105. 0.96 0.06 14555002 91 0.166 0.003 7. 14555002 92 1.37 120. 51. 127. 0.20 0.01 14555002 93 0.035 0.001 8. 14555002 94 1.37 120. 52. 132. 4.49 0.25 14555002 95 0.779 0.048 10. 14555002 96 1.37 120. 53. 131. 3.02 0.11 14555002 97 0.524 0.018 9. 14555002 98 1.37 120. 53. 133. 6.22 0.25 14555002 99 1.079 0.023 11. 14555002 100 1.37 120. 54. 135. 6.46 0.34 14555002 101 1.120 0.067 12. 14555002 102 1.37 120. 56. 140. 5.81 0.18 14555002 103 1.007 0.018 14. 14555002 104 1.37 120. 58. 143. 5.49 0.23 14555002 105 0.952 0.048 15. 14555002 106 1.37 120. 60. 147. 2.17 0.08 14555002 107 0.376 0.007 16. 14555002 108 2.37 70. 38. 91. 5.38 0.25 14555002 109 0.933 0.014 1. 14555002 110 2.37 70. 38. 92. 5.36 0.30 14555002 111 0.930 0.016 2. 14555002 112 2.37 70. 40. 95. 6.10 0.21 14555002 113 1.059 0.016 3. 14555002 114 2.37 70. 40. 97. 5.94 0.20 14555002 115 1.032 0.017 4. 14555002 116 2.37 70. 42. 99. 5.76 0.24 14555002 117 5. 14555002 118 2.37 70. 44. 103. 3.15 0.12 14555002 119 0.546 0.010 6. 14555002 120 2.37 70. 44. 105. 1.51 0.16 14555002 121 0.263 0.005 7. 14555002 122 2.37 70. 51. 127. 0.33 0.02 14555002 123 0.057 0.001 8. 14555002 124 2.37 70. 52. 132. 4.79 0.26 14555002 125 0.831 0.051 10. 14555002 126 2.37 70. 53. 131. 3.23 0.12 14555002 127 0.560 0.018 9. 14555002 128 2.37 70. 53. 133. 6.42 0.27 14555002 129 1.113 0.019 11. 14555002 130 2.37 70. 54. 135. 6.48 0.36 14555002 131 1.125 0.067 12. 14555002 132 2.37 70. 56. 140. 5.57 0.19 14555002 133 0.966 0.016 14. 14555002 134 2.37 70. 58. 143. 5.36 0.23 14555002 135 0.930 0.045 15. 14555002 136 2.37 70. 60. 147. 2.20 0.11 14555002 137 0.382 0.008 16. 14555002 138 3.60 70. 38. 91. 5.42 0.24 14555002 139 0.900 0.011 1. 14555002 140 3.60 70. 38. 92. 5.74 0.34 14555002 141 0.952 0.013 2. 14555002 142 3.60 70. 40. 95. 6.02 0.18 14555002 143 1.000 0.028 3. 14555002 144 3.60 70. 40. 97. 6.06 0.17 14555002 145 1.006 0.028 4. 14555002 146 3.60 70. 42. 99. 6.03 0.25 14555002 147 5. 14555002 148 3.60 70. 44. 103. 3.15 0.12 14555002 149 0.517 0.017 6. 14555002 150 3.60 70. 44. 105. 1.63 0.07 14555002 151 0.270 0.008 7. 14555002 152 3.60 70. 51. 127. 0.49 0.03 14555002 153 0.082 0.003 8. 14555002 154 3.60 70. 52. 132. 4.84 0.27 14555002 155 0.803 0.065 10. 14555002 156 3.60 70. 53. 131. 3.42 0.15 14555002 157 0.568 0.034 9. 14555002 158 3.60 70. 53. 133. 6.49 0.26 14555002 159 1.078 0.033 11. 14555002 160 3.60 70. 54. 135. 6.20 0.36 14555002 161 1.029 0.087 12. 14555002 162 3.60 70. 56. 140. 5.36 0.22 14555002 163 0.889 0.027 14. 14555002 164 3.60 70. 58. 143. 5.07 0.25 14555002 165 0.841 0.068 15. 14555002 166 3.60 70. 60. 147. 1.96 0.08 14555002 167 0.326 0.010 16. 14555002 168 4.49 250. 38. 91. 5.00 0.25 14555002 169 0.889 0.014 1. 14555002 170 4.49 250. 38. 92. 5.11 0.31 14555002 171 0.909 0.017 2. 14555002 172 4.49 250. 40. 97. 5.92 0.23 14555002 173 1.052 0.017 4. 14555002 174 4.49 250. 42. 99. 5.63 0.28 14555002 175 5. 14555002 176 4.49 250. 44. 103. 3.30 0.18 14555002 177 0.586 0.010 6. 14555002 178 4.49 250. 44. 105. 1.44 0.13 14555002 179 0.255 0.004 7. 14555002 180 4.49 250. 51. 127. 0.69 0.05 14555002 181 0.122 0.002 8. 14555002 182 4.49 250. 52. 132. 4.90 0.30 14555002 183 0.870 0.053 10. 14555002 184 4.49 250. 53. 131. 3.72 0.16 14555002 185 0.662 0.021 9. 14555002 186 4.49 250. 53. 133. 6.27 0.30 14555002 187 1.114 0.019 11. 14555002 188 4.49 250. 54. 135. 6.45 0.39 14555002 189 1.147 0.068 12. 14555002 190 4.49 250. 56. 140. 5.29 0.21 14555002 191 0.940 0.016 14. 14555002 192 4.49 250. 58. 143. 4.71 0.23 14555002 193 0.837 0.041 15. 14555002 194 4.49 250. 60. 147. 2.06 0.11 14555002 195 0.367 0.009 16. 14555002 196 14.8 75. 38. 91. 4.34 0.22 14555002 197 0.940 0.021 1. 14555002 198 14.8 75. 38. 92. 4.37 0.27 14555002 199 0.947 0.025 2. 14555002 200 14.8 75. 40. 95. 4.95 0.19 14555002 201 1.074 0.024 3. 14555002 202 14.8 75. 40. 97. 4.88 0.20 14555002 203 1.057 0.028 4. 14555002 204 14.8 75. 42. 99. 4.61 0.24 14555002 205 5. 14555002 206 14.8 75. 44. 103. 2.94 0.14 14555002 207 0.636 0.015 6. 14555002 208 14.8 75. 44. 105. 1.92 0.10 14555002 209 0.417 0.009 7. 14555002 210 14.8 75. 51. 127. 1.64 0.11 14555002 211 0.355 0.008 8. 14555002 212 14.8 75. 52. 132. 3.89 0.24 14555002 213 0.843 0.053 10. 14555002 214 14.8 75. 53. 131. 4.43 0.19 14555002 215 0.959 0.034 9. 14555002 216 14.8 75. 53. 133. 4.91 0.24 14555002 217 1.064 0.025 11. 14555002 218 14.8 75. 54. 135. 5.36 0.32 14555002 219 1.162 0.071 12. 14555002 220 14.8 75. 56. 140. 4.20 0.17 14555002 221 0.911 0.021 14. 14555002 222 14.8 75. 58. 143. 3.67 0.18 14555002 223 0.796 0.041 15. 14555002 224 14.8 75. 60. 147. 1.47 0.07 14555002 225 0.318 0.008 16. 14555002 226 ENDDATA 178 0 14555002 227 ENDSUBENT 226 0 1455500299999 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