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