ENTRY 10506 20190722 14541050600000001 SUBENT 10506001 20190722 14541050600100001 BIB 14 36 1050600100002 TITLE The ratio of the uranium-238 to uranium-235 fission 1050600100003 cross sections from 5.3 to 10.3 MeV 1050600100004 AUTHOR (J.W.Meadows) 1050600100005 INSTITUTE (1USAANL) 1050600100006 REFERENCE (J,NSE,58,255,1975) 1050600100007 (R,ANL-NDM-83,1983) Revised data in table 1050600100008 REL-REF (M,10237003,J.W.Meadows,J,NSE,49,310,1972) 1050600100009 Description of experiment 1050600100010 FACILITY (DYNAM,1USAANL) Argonne 8 MeV Tandem Dynamitron 1050600100011 INC-SOURCE (D-D) Deuterium gas in a 2-cm-long cell filled to 1050600100012 2 atm. 1050600100013 SAMPLE Samples deposited on 0.25-mm thick polished stainless 1050600100014 steel or 0.13-mm thick Mo backings by electroplating 1050600100015 or by vacuum evaporation. 1050600100016 Below 2 MeV, deposit diameter 2.5 cm, approximate 1050600100017 thicknesses either 150 or 500 ug/cm2. 1050600100018 Above 3 MeV, deposit diameter 5 cm, thickness 1050600100019 approximately 500 ug/cm2. 1050600100020 DETECTOR (FISCH) Low-mass double ionization chamber using 1050600100021 methane as the counting gas. 1050600100022 METHOD (TOF) Time-of-flight used to reduce and measure 1050600100023 time-independent background. 1050600100024 Sample mass ratios for normalization measured by 1050600100025 comparing thermal thermal fission rate of 235U 1050600100026 samples and 238U samples containing 10% 235U. 1050600100027 Sample masses also measured by calorimetric analysis. 1050600100028 ANALYSIS Ratios normalized at 2.500, 2.890, 3.256 MeV. 1050600100029 CORRECTION Data corrected for inelastic scattering from target and1050600100030 ion chamber structure and for neutrons produced from 1050600100031 deuterium in the energy range of 1 to 3 MeV. 1050600100032 STATUS (APRVD) J.W.Meadows, 1984/3/2. 1050600100033 HISTORY (19750508C) 1050600100034 (19830823A) Converted to REACTION formalism 1050600100035 (19831230A) Revised as per ANL-NDM-83. 1050600100036 (20040427U) Updated to new date formats, lower case. 1050600100037 (20190722A) On. Major revision in 002. 1050600100038 ENDBIB 36 0 1050600100039 NOCOMMON 0 0 1050600100040 ENDSUBENT 39 0 1050600199999 SUBENT 10506002 20190722 14541050600200001 BIB 6 21 1050600200002 REACTION 1((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG)) 1050600200003 2(92-U-238(N,F),,SIG) 1050600200004 MONITOR 2(92-U-235(N,F),,SIG) 1050600200005 MONIT-REF 2(,,3,ENDF/B-V,,1978) 1050600200006 ERR-ANALYS1(ERR-T) Total error 1050600200007 - secondary source reactions (20% of correction) 1050600200008 - propagation from neutron energy error (~20% of the 1050600200009 energy resolution) 1050600200010 (ERR-1,,,F) Normalization of shape ratio: 1050600200011 - calorimetric analysis (0.50%) 1050600200012 - alpha counting excluding statistics (0.60%) 1050600200013 - thickness correction (0.18%) 1050600200014 - extrapolation (0.10%) 1050600200015 - dead time correction (0.25%) 1050600200016 - scattering correction (0.60%) 1050600200017 - statistical - alpha counting etc. (0.42%) 1050600200018 (ERR-2,,,U) Uncorrelated error, which principle due to 1050600200019 the counting statistics, but a part is based on the 1050600200020 consistency of repeated measurements. 1050600200021 STATUS (TABLE) Table XIII of ANL-NDM-83 1050600200022 HISTORY (20190722A) On. ERR-S -> ERR-2. ERR-1 added. 1050600200023 ENDBIB 21 0 1050600200024 COMMON 1 3 1050600200025 ERR-1 1050600200026 PER-CENT 1050600200027 1.12 1050600200028 ENDCOMMON 3 0 1050600200029 DATA 6 22 1050600200030 EN EN-RSL-FW DATA 1ERR-2 1ERR-T 1DATA 21050600200031 MEV MEV NO-DIM PER-CENT PER-CENT B 1050600200032 5.334 0.070 0.5264 1.05 1.39 0.551 1050600200033 5.439 0.216 0.5242 0.82 1.32 0.548 1050600200034 5.622 0.204 0.5380 0.73 1.31 0.565 1050600200035 5.826 0.191 0.5652 0.73 1.35 0.605 1050600200036 6.168 0.178 0.5735 0.74 1.42 0.683 1050600200037 6.430 0.165 0.620 0.72 1.27 0.821 1050600200038 6.692 0.154 0.617 0.74 1.23 0.896 1050600200039 6.949 0.144 0.618 0.67 1.19 0.949 1050600200040 7.204 0.137 0.606 0.75 1.25 0.989 1050600200041 7.457 0.132 0.606 0.68 1.21 1.035 1050600200042 7.709 0.128 0.584 0.75 1.25 1.025 1050600200043 7.960 0.126 0.576 0.74 1.24 1.025 1050600200044 8.208 0.124 0.570 0.80 1.27 1.017 1050600200045 8.455 0.122 0.571 0.67 1.21 1.018 1050600200046 8.690 0.120 0.567 0.78 1.33 1.008 1050600200047 8.946 0.11 0.580 0.75 1.42 1.028 1050600200048 9.191 0.120 0.578 0.71 1.51 1.022 1050600200049 9.433 0.121 0.589 0.74 1.68 1.038 1050600200050 9.675 0.121 0.583 0.76 1.81 1.025 1050600200051 9.818 0.122 0.591 0.76 1.87 1.037 1050600200052 10.160 0.124 0.570 0.77 1.86 0.995 1050600200053 10.400 0.126 0.554 0.76 1.73 0.964 1050600200054 ENDDATA 24 0 1050600200055 ENDSUBENT 54 0 1050600299999 ENDENTRY 2 0 1050699999999