ENTRY            14062   20051214                             13391406200000001 
SUBENT        14062001   20051214                             13391406200100001 
BIB                 12         15                                 1406200100002 
INSTITUTE  (1USALRL)                                              1406200100003 
REFERENCE  (J,PR,107,1642,1957)                                   1406200100004 
AUTHOR     (S.R.Gunn,H.G.Hicks,H.B.Levy,P.C.Stevenson)            1406200100005 
TITLE      Calorimetric Determination of the Average Total Kinetic1406200100006 
            Energy of Fragments from Fission of U235              1406200100007 
FACILITY   (REAC,1USALRL) Water boiled reactor                    1406200100008 
INC-SOURCE Nominal 14 MeV neutron                                 1406200100009 
METHOD     (TOF)                                                  1406200100010 
            Number of fissions determined by a 99Mo radiochemical 1406200100011 
            analysis                                              1406200100012 
DECAY-DATA (42-MO-99,66.00HR)  Half-life of 66.00 +/- 0.15 hr.    1406200100013 
DETECTOR   (LONGC) Fission calorimeter                            1406200100014 
PART-DET   (N)                                                    1406200100015 
SAMPLE     Uranium foils 93 % U235, 240 mg, in aluminum layer     1406200100016 
HISTORY    (20051214C) DR                                         1406200100017 
ENDBIB              15          0                                 1406200100018 
COMMON               1          3                                 1406200100019 
EN                                                                1406200100020 
MEV                                                               1406200100021 
14.                                                               1406200100022 
ENDCOMMON            3          0                                 1406200100023 
ENDSUBENT           22          0                                 1406200199999 
SUBENT        14062002   20051214                             13391406200200001 
BIB                  3          4                                 1406200200002 
REACTION   (92-U-235(N,F),,AKE,FF)                                1406200200003 
            Average kinetic energy                                1406200200004 
ERR-ANALYS (ERR-T) Total uncertainty                              1406200200005 
STATUS     Data taken from the article                            1406200200006 
ENDBIB               4          0                                 1406200200007 
NOCOMMON             0          0                                 1406200200008 
DATA                 2          1                                 1406200200009 
DATA       ERR-T                                                  1406200200010 
MEV        MEV                                                    1406200200011 
166.       2.                                                     1406200200012 
ENDDATA              3          0                                 1406200200013 
ENDSUBENT           12          0                                 1406200299999 
ENDENTRY             2          0                                 1406299999999