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