ENTRY 10290 20011227 00001029000000001 SUBENT 10290001 20011227 00001029000100001 BIB 12 25 1029000100002 INSTITUTE (1USALAS) 1029000100003 REFERENCE (J,PR/C,4,220,1971) 1029000100004 (R,LA-DC-12433,1972) 1029000100005 AUTHOR (M.G.Silbert,D.W.Bergen) 1029000100006 TITLE Sub-threshold neutron induced fission in 238U 1029000100007 INC-SOURCE (EXPLO) Nuclear explosive device Physics-8 shot. 1029000100008 SAMPLE UO2 sample, 0.9 mg/cm**2 of 238U, vacuum evaporated on 1029000100009 3.6E-04 cm stainless steel backing with a total of 1029000100010 3.8 mg of 238U in the neutron beam. Source was stated 1029000100011 to have 99.9999% 238U, 0.00002% 234U and <0.00005% 1029000100012 235U. 1029000100013 METHOD (TOF) Time-of-flight with a flight path 244 m long. 1029000100014 Fission measurement. 1029000100015 DETECTOR (SOLST) Two semiconductor detectors. only one signal 1029000100016 analyzed. 1029000100017 CORRECTION Correction for 235U impurity in sample. 1029000100018 ERR-ANALYS (DATA-ERR) Quoted uncertainties are standard deviations1029000100019 based on statistical uncertainty and estimate of 1029000100020 reliability of fission fragment counting from film 1029000100021 record at 25%. 1029000100022 STATUS (APRVD) Approved by author. 1029000100023 Data taken from reference. 1029000100024 HISTORY (19721209C) 1029000100025 (19830117A) Converted to REACTION formalism 1029000100026 (20011227A) Updated to new date formats, lower case. 1029000100027 ENDBIB 25 0 1029000100028 NOCOMMON 0 0 1029000100029 ENDSUBENT 28 0 1029000199999 SUBENT 10290002 20011227 00001029000200001 BIB 2 6 1029000200002 REACTION (92-U-238(N,F),,WID,,AV) 1029000200003 ANALYSIS (AREA) 1029000200004 Average fission width quoted here is an average over 1029000200005 37.,66.,103.,117.,165.,190.,209., and 237. eV 1029000200006 resonances and gives an upper limit of 0.13E-06 eV 1029000200007 to the fission width at 95% confidence level. 1029000200008 ENDBIB 6 0 1029000200009 NOCOMMON 0 0 1029000200010 DATA 4 1 1029000200011 EN-MIN EN-MAX DATA DATA-ERR 1029000200012 EV EV EV EV 1029000200013 37. 327. 0.03 E-06 0.05 E-06 1029000200014 ENDDATA 3 0 1029000200015 ENDSUBENT 14 0 1029000299999 SUBENT 10290003 20011227 00001029000300001 BIB 2 2 1029000300002 REACTION (92-U-238(N,F),,SIG,,AV) 1029000300003 MONITOR (92-U-235(N,F),,SIG) Flux measurement. 1029000300004 ENDBIB 2 0 1029000300005 NOCOMMON 0 0 1029000300006 DATA 4 2 1029000300007 EN-MIN EN-MAX DATA DATA-ERR 1029000300008 EV EV MICRO-B MICRO-B 1029000300009 1.0 E+04 3.0 E+04 61. 24. 1029000300010 3.0 E+04 1.0 E+05 36. 14. 1029000300011 ENDDATA 4 0 1029000300012 ENDSUBENT 11 0 1029000399999 ENDENTRY 3 0 1029099999999