ENTRY            21485   19800429                             00002148500000001 
SUBENT        21485001   19800429                             00002148500100001 
BIB                 12         20                                 2148500100002 
INSTITUTE  (2FR SAC)                                              2148500100003 
REFERENCE  (R,CEA-652,23,58) CHAPTER IV.                          2148500100004 
AUTHOR     (M.JACOB)                                              2148500100005 
TITLE      -A COMPARISON OF THE AVERAGE NUMBER OF NEUTRONS EMITTED2148500100006 
            BY FISSION OF PU-239 AND U-233 -.                     2148500100007 
FACILITY   (REAC ) THERMAL COLUMN.                                2148500100008 
INC-SOURCE (THCOL) THERMAL PILE, SACLAY.                          2148500100009 
SAMPLE     .A DEPOSIT OF 7.5 MG PLUTONIUM AND 4 MG U-233, AS      2148500100010 
            OXIDE ON ALUMINIUM FOILS.                             2148500100011 
DETECTOR   (BF3  ) BF3 COUNTERS ENRICHED IN B-10 FOR FISSION      2148500100012 
            NEUTRONS.                                             2148500100013 
           (FISCH) FISSION CHAMBER, DIVIDED INTO TWO COMPARTMENTS 2148500100014 
            TO COUNT SIMULATNEOUSLY FRAGMENTS FROM THE PU-239     2148500100015 
            AND U-233 SAMPLES.                                    2148500100016 
PART-DET   (N    ) FISSION NEUTRONS IN COINCIDENCE WITH           2148500100017 
           (FF   ) FISSION FRAGMENTS.                             2148500100018 
STATUS     .TEXT, PAGE 23.                                        2148500100019 
HISTORY    (800402C)                                              2148500100020 
           (800429E)                                              2148500100021 
ERR-ANALYS .STATISTICAL STANDARD DEVIATIONS.                      2148500100022 
ENDBIB              20          0                                 2148500100023 
NOCOMMON             0          0                                 2148500100024 
ENDSUBENT           23          0                                 2148500199999 
SUBENT        21485002   19810204                             00002148500200001 
BIB                  4          6                                 2148500200002 
REACTION   ((94-PU-239(N,F),,NU,,MXW)/(92-U-233(N,F),,NU,,MXW))   2148500200003 
            RATIO OF NU FOR PU-239 TO U-233.                      2148500200004 
INC-SPECT  THERMAL NEUTRON SPECTRUM.                              2148500200005 
STATUS     .TEXT, PAGE 23.                                        2148500200006 
HISTORY    (800402C)                                              2148500200007 
           (800429E)                                              2148500200008 
ENDBIB               6          0                                 2148500200009 
NOCOMMON             0          0                                 2148500200010 
DATA                 3          1                                 2148500200011 
EN-DUMMY   RATIO      RATIO-ERR                                   2148500200012 
EV         NO-DIM     NO-DIM                                      2148500200013 
 2.5300E-02 1.1650E+00 2.0000E-02                                 2148500200014 
ENDDATA              3          0                                 2148500200015 
ENDSUBENT           14          0                                 2148500299999 
ENDENTRY             2          0                                 2148599999999