ENTRY 12714 20200925 14731271400000001 SUBENT 12714001 20200925 14731271400100001 BIB 12 68 1271400100002 TITLE The fission cross section of plutonium-240 relative to 1271400100003 uranium-235 from 0.35 to 9.6 MeV 1271400100004 AUTHOR (J.W.Meadows) 1271400100005 INSTITUTE (1USAANL) 1271400100006 REFERENCE (J,NSE,79,233,1981) 1271400100007 (R,ANL-NDM-83,1983) 1271400100008 Full description with revised data table 1271400100009 FACILITY (DYNAM,1USAANL) Argonne 8 MeV Tandem Dynamitron 1271400100010 INC-SOURCE (P-LI7) En < 5 MeV 1271400100011 (D-D) En > 5 MeV 1271400100012 DETECTOR (FISCH) Low mass ionization chamber operated as a flow 1271400100013 counter using methane as a count gas. 1271400100014 Plutonium and uranium samples placed back-to-back, and 1271400100015 a second measurement was done with sample positions 1271400100016 reversed. 1271400100017 SAMPLE Thin layers of Pu and U (2.54 cm diam.) deposited onto 1271400100018 stainless steel plates (0.25 mm thick) or molybdenum 1271400100019 plates (0.13 mm thick). 1271400100020 The sample masses were measured by three methods: 1271400100021 - Low geometry alpha counting and calculated specific 1271400100022 activities, 1271400100023 - Relative thermal fission rates of 235U samples and 1271400100024 240Pu samples containing 9% 239Pu, 1271400100025 - Isotopic dilution analysis. 1271400100026 ------------------------------------------------------ 1271400100027 Sample# Weight(g) Isotopic composition (at.%) 1271400100028 -------------------------------------------------------1271400100029 238Pu 239Pu 240Pu 241Pu 242Pu 241Am1271400100030 -------------------------------------------------------1271400100031 240Pu-38 0.0754 0.012 0.677 98.386 0.426 0.370 0.1281271400100032 240Pu-39 0.260 0.012 0.674 98.394 0.421 0.370 0.1291271400100033 240Pu-40 0.0945 0.009 9.490 89.634 0.381 0.338 0.1481271400100034 240Pu-41 0.333 0.016 9.330 89.825 0.384 0.336 0.1101271400100035 -------------------------------------------------------1271400100036 234U 235U 236U 238U 1271400100037 -------------------------------------------------------1271400100038 235U 5-1 1.066 1.032 98.402 0.445 0.121 1271400100039 235U 5-2 0.832 1.032 98.402 0.445 0.121 1271400100040 -------------------------------------------------------1271400100041 CORRECTION Corrected for 1271400100042 - backgrounds 1271400100043 - extrapolation to zero bias 1271400100044 - neutron scatter from experimental apparatus 1271400100045 - deposit thickness 1271400100046 - second order momentum transfer 1271400100047 - fragment angular distribution effects 1271400100048 - presence of minor isotopes 1271400100049 - secondary neutron source reactions 1271400100050 ERR-ANALYS (ERR-T) Total error consisting of 1271400100051 (ERR-1,,,U) Uncorrelated error 1271400100052 (ERR-2,,,F) 234U half-life (0.08%) 1271400100053 (ERR-3,,,F) 240Pu half-life (0.03%) 1271400100054 (ERR-4,,,F) 239Pu/235U thermal ratio (0.17%) 1271400100055 (ERR-5,,,F) Isotopic analysis (0.14%) 1271400100056 (ERR-6,,,F) Isotopic dilution (0.24%) 1271400100057 (ERR-7,,,F) Calorimetry (0.16%) 1271400100058 (ERR-8,,,F) Alpha-counting system (0.20%) 1271400100059 (ERR-9,,,F) Thickness correction (0.22%) 1271400100060 (ERR-10,,,F) Zero bias extrapolation (0.40%) 1271400100061 (ERR-11,,,F) Scattering correction (0.30%) 1271400100062 (ERR-12,,,F) Statistics in normalization point(0.82%) 1271400100063 (ERR-13,,0.9) Secondary source neutrons (<0.9%) 1271400100064 (ERR-14,,3.4) Neutron energy (<3.4%) 1271400100065 STATUS (TABLE) Table XVI of Report ANL-NDM-83 1271400100066 (APRVD) J.W.Meadows, 1984/3/2. 1271400100067 HISTORY (19811210C) 1271400100068 (19840206A) Revised as per ANL-NDM-83. 1271400100069 (20200925A) On. Recompiled. 1271400100070 ENDBIB 68 0 1271400100071 COMMON 11 6 1271400100072 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 1271400100073 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 1271400100074 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1271400100075 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1271400100076 0.08 0.03 0.17 0.14 0.24 0.16 1271400100077 0.20 0.22 0.40 0.30 0.82 1271400100078 ENDCOMMON 6 0 1271400100079 ENDSUBENT 78 0 1271400199999 SUBENT 12714002 20200925 14731271400200001 BIB 5 7 1271400200002 REACTION 1((94-PU-240(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1271400200003 2(94-PU-240(N,F),,SIG) 1271400200004 ANALYSIS 1 Shape ratio normalized to absolute ratio at 2.061, 1271400200005 2.322, 2.566, 2.803 and 3.046 MeV. 1271400200006 MONITOR 2(92-U-235(N,F),,SIG) 1271400200007 MONIT-REF 2(,,3,ENDF/B-V,,1978) 1271400200008 HISTORY (20200925A) On. ERR-T/S->ERR-1/T. 8 numbers corrected. 1271400200009 ENDBIB 7 0 1271400200010 NOCOMMON 0 0 1271400200011 DATA 6 55 1271400200012 EN EN-RSL-FW DATA 1ERR-1 1ERR-T 1DATA 21271400200013 MEV MEV NO-DIM PER-CENT PER-CENT B 1271400200014 0.335 0.062 0.1121 4.09 5.73 0.1394 1271400200015 0.393 0.060 0.1554 3.08 7.39 0.1884 1271400200016 0.450 0.058 0.2242 2.07 7.31 0.2655 1271400200017 0.506 0.056 0.334 1.75 8.17 0.389 1271400200018 0.560 0.054 0.470 1.71 6.79 0.542 1271400200019 0.616 0.053 0.612 1.65 4.71 0.700 1271400200020 0.669 0.051 0.728 1.65 3.44 0.830 1271400200021 0.715 0.060 0.803 1.64 3.35 0.913 1271400200022 0.768 0.058 0.926 1.64 2.82 1.052 1271400200023 0.821 0.058 1.028 1.65 2.56 1.173 1271400200024 0.873 0.056 1.122 1.64 2.36 1.298 1271400200025 0.925 0.055 1.163 1.65 2.27 1.378 1271400200026 0.979 0.055 1.198 1.65 2.19 1.457 1271400200027 1.030 0.053 1.185 1.65 1.98 1.442 1271400200028 1.074 0.072 1.232 1.70 2.02 1.497 1271400200029 1.178 0.072 1.207 1.71 2.02 1.470 1271400200030 1.281 0.070 1.238 1.71 2.01 1.518 1271400200031 1.385 0.068 1.239 1.71 2.01 1.533 1271400200032 1.488 0.066 1.228 1.71 2.01 1.535 1271400200033 1.590 0.064 1.259 1.71 2.01 1.590 1271400200034 1.692 0.062 1.273 1.71 2.01 1.625 1271400200035 1.762 0.121 1.241 1.66 1.97 1.594 1271400200036 1.856 0.118 1.266 1.66 1.97 1.635 1271400200037 1.926 0.117 1.287 1.61 1.93 1.667 1271400200038 2.061 0.113 1.313 0.63 1.23 1.703 1271400200039 2.322 0.109 1.312 0.64 1.23 1.685 1271400200040 2.566 0.102 1.320 0.64 1.23 1.666 1271400200041 2.803 0.099 1.348 0.64 1.23 1.671 1271400200042 2.935 0.096 1.366 1.58 1.90 1.674 1271400200043 3.046 0.093 1.395 0.62 1.23 1.694 1271400200044 3.228 0.088 1.404 1.63 1.95 1.683 1271400200045 3.552 0.084 1.451 1.64 1.97 1.697 1271400200046 3.793 0.080 1.413 1.65 2.01 1.623 1271400200047 4.046 0.078 1.437 1.66 2.02 1.624 1271400200048 4.308 0.076 1.403 1.70 2.11 1.574 1271400200049 4.559 0.075 1.432 1.70 2.20 1.583 1271400200050 4.760 0.072 1.443 1.81 2.09 1.567 1271400200051 5.220 0.233 1.430 1.71 2.01 1.503 1271400200052 5.510 0.211 1.457 1.71 2.01 1.526 1271400200053 5.791 0.195 1.467 1.77 2.06 1.562 1271400200054 6.066 0.183 1.440 1.73 2.06 1.646 1271400200055 6.337 0.170 1.379 1.73 2.06 1.758 1271400200056 6.610 0.158 1.344 1.69 2.00 1.901 1271400200057 6.866 0.147 1.326 1.73 2.03 2.002 1271400200058 7.125 0.139 1.311 1.76 2.05 2.099 1271400200059 7.382 0.134 1.290 1.75 2.04 2.175 1271400200060 7.635 0.129 1.264 1.74 2.03 2.203 1271400200061 7.888 0.126 1.233 1.73 2.02 2.187 1271400200062 8.143 0.124 1.227 1.72 2.02 2.189 1271400200063 8.387 0.122 1.249 1.73 2.02 2.227 1271400200064 8.605 0.120 1.251 1.75 2.04 2.226 1271400200065 8.860 0.120 1.250 1.80 2.08 2.218 1271400200066 9.128 0.120 1.235 1.84 2.12 2.185 1271400200067 9.351 0.121 1.250 1.84 2.12 2.206 1271400200068 9.597 0.121 1.237 1.80 2.08 2.176 1271400200069 ENDDATA 57 0 1271400200070 ENDSUBENT 69 0 1271400299999 ENDENTRY 2 0 1271499999999