ENTRY            21430   19800318                             00002143000000001 
SUBENT        21430001   19800318                             00002143000100001 
BIB                 11         17                                 2143000100002 
INSTITUTE  (2UK HAR)                                              2143000100003 
REFERENCE  (R,AERE-NP/R-2104,4,5703) ABSTRACT.                    2143000100004 
           (R,AERE-N/R-890,,5203)                                 2143000100005 
AUTHOR     (H.S.COCKCROFT)                                        2143000100006 
TITLE      -RATIO OF FISSION CROSS SECTIONS OF U-235/PU-239 -.    2143000100007 
FACILITY   (REAC ) BEPO REACTOR.                                  2143000100008 
INC-SOURCE (THCOL) THERMAL BEAM FROM REACTOR.                     2143000100009 
SAMPLE     .NATURAL URANIUM, EVAPORATED ONTO A FOIL, 1 MG OVER    2143000100010 
            A DISC 0.75 INCH DIAMETER,                            2143000100011 
            PLUTONIUM DEPOSITED FROM SOLUTION AS NITRATE          2143000100012 
            WHICH WAS THEN IGNITED. QUANTITY OF MATERIAL          2143000100013 
            ESTIMATED BY ALPHA COUNTING.                          2143000100014 
METHOD     .NO DETAILS.                                           2143000100015 
STATUS     (NDD  ) CORRESPONDS TO VALUE GIVEN IN AERE-NP/R-2104   2143000100016 
HISTORY    (800313T)                                              2143000100017 
           (800318E)                                              2143000100018 
ERR-ANALYS .ONE STANDARD DEVIATION, NO DETAILS.                   2143000100019 
ENDBIB              17          0                                 2143000100020 
NOCOMMON             0          0                                 2143000100021 
ENDSUBENT           20          0                                 2143000199999 
SUBENT        21430002   19801107                             00002143000200001 
BIB                  3          4                                 2143000200002 
REACTION   ((94-PU-239(N,F),,SIG,,MXW)/(92-U-235(N,F),,SIG,,MXW)) 2143000200003 
            RATIO OF PU-239 TO U-235.                             2143000200004 
INC-SPECT  MAXWELLIAN NEUTRON SPECTRUM.                           2143000200005 
STATUS     (NDD  )                                                2143000200006 
ENDBIB               4          0                                 2143000200007 
NOCOMMON             0          0                                 2143000200008 
DATA                 3          1                                 2143000200009 
EN-DUMMY   RATIO      RATIO-ERR                                   2143000200010 
EV         NO-DIM     NO-DIM                                      2143000200011 
 2.5300E-02 1.4050E+00 9.0000E-03                                 2143000200012 
ENDDATA              3          0                                 2143000200013 
ENDSUBENT           12          0                                 2143000299999 
SUBENT        21430003   19800318                             00002143000300001 
BIB                  2          4                                 2143000300002 
REACTION   ((94-PU-239(N,F),,SIG)/(92-U-235(N,F),,SIG))           2143000300003 
            RATIO OF FISSION CROSS SECTIONS CORRECTED             2143000300004 
            TO 2200 M/SEC.                                        2143000300005 
STATUS     (NDD  )                                                2143000300006 
ENDBIB               4          0                                 2143000300007 
NOCOMMON             0          0                                 2143000300008 
DATA                 3          1                                 2143000300009 
EN         RATIO      RATIO-ERR                                   2143000300010 
EV         NO-DIM     NO-DIM                                      2143000300011 
 2.5300E-02 1.2600E+00 5.0000E-02                                 2143000300012 
ENDDATA              3          0                                 2143000300013 
ENDSUBENT           12          0                                 2143000399999 
ENDENTRY             3          0                                 2143099999999