ENTRY            21555   19840416                             00002155500000001 
SUBENT        21555001   19840416                             00002155500100001 
BIB                 13         27                                 2155500100002 
INSTITUTE  (2JPNKTO) RESEARCH REACTOR INSTSTUTE.                  2155500100003 
           (2JPNNII) NIIGATA UNIVERSITY, H.N, M.Y                 2155500100004 
REFERENCE  (J,JIN,38,203,76)                                      2155500100005 
AUTHOR     (H.NAKAHARA,M.YANOKURA,Y.NAKAGOME,T.HASHIMOTO)         2155500100006 
TITLE      -THERMAL NEUTRON INDUCED FISSION OF RA-226 -.          2155500100007 
FACILITY   (REAC ) HEAVY WATER MODERATED REACTOR OF K.U.R.        2155500100008 
INC-SOURCE (THCOL) THERMAL COLUMN, FLUX 1.6 10*9 N/CM*2/SEC.      2155500100009 
SAMPLE     .RA-226 CHLORIDE SOLUTION, FROM UK, EVAPOURATED TO     2155500100010 
            DRYNESS ON THE GOLD SURFACE OF THE SOLID STATE        2155500100011 
            DETECTORS. A TOTAL OF 9.7 MICRO-CI FROM COUNTING      2155500100012 
            THE 186 KEV GAMMAS IN DECAY.                          2155500100013 
METHOD     .PROMT DETECTION OF FISSION FRAGMENTS.                 2155500100014 
DETECTOR   (SOLST) TWO GOLD PLATED SURFACE BARRIER DETECTORS,     2155500100015 
            2.5 CM DIAMETER, FACE TO FACE IN A SCATTERING         2155500100016 
            CHAMBER, 0.6 CM APART. DETECTORS WERE OPERATED BOTH   2155500100017 
            IN SINGLES AND COINCIDENCE MODE.                      2155500100018 
MONITOR    (79-AU-197(N,G)79-AU-198-G,,SIG,,MXW) THERMAL FLUX     2155500100019 
            MONITORED USING A VALUE OF 98.8B.                     2155500100020 
           .THE CADMIUM RATIO OF THE NEUTRON SPECTRUM WAS         2155500100021 
            MEASURED TO BE GREATER THEN 10,000.                   2155500100022 
STATUS     .TEXT, JIN,38,203.                                     2155500100023 
HISTORY    (800605C)                                              2155500100024 
           (800612E)                                              2155500100025 
           (840106U) A.P.T. JAPAN CODE CHANGED TO JPN             2155500100026 
           (840106E)                                              2155500100027 
ERR-ANALYS .AN UPPER LIMIT TO THE CROSS SECTION IS GIVEN AT ONE   2155500100028 
            STANDARD DEVAITION.                                   2155500100029 
ENDBIB              27          0                                 2155500100030 
COMMON               1          3                                 2155500100031 
MONIT                                                             2155500100032 
B                                                                 2155500100033 
 9.8800E+01                                                       2155500100034 
ENDCOMMON            3          0                                 2155500100035 
ENDSUBENT           34          0                                 2155500199999 
SUBENT        21555002   19810404                             00002155500200001 
BIB                  5          9                                 2155500200002 
REACTION   (88-RA-226(N,F),,SIG,,MXW) THERMAL FISSION CROSS SECT. 2155500200003 
INC-SPECT  PURE THERMAL NEUTRON MAXWELLIAN SPECTRUM WITH          2155500200004 
            A CADMIUM RATION OF GREATER THAN 10,000.              2155500200005 
COMMENT    .IN SINGLES 102 EVENTS IN 140,000 SECONDS COUNTING WER 2155500200006 
            OBSERVED, IN COINCIDENCE ONLY ONE EEVENT IN 23,000    2155500200007 
            SECONDS WAS OBSERVED.                                 2155500200008 
STATUS     .TEXT, JIN,38,203.                                     2155500200009 
HISTORY    (800605C)                                              2155500200010 
           (800612E)                                              2155500200011 
ENDBIB               9          0                                 2155500200012 
NOCOMMON             0          0                                 2155500200013 
DATA                 2          1                                 2155500200014 
EN-DUMMY   DATA-MAX                                               2155500200015 
EV         MB                                                     2155500200016 
 2.5300E-02 7.0000E-03                                            2155500200017 
ENDDATA              3          0                                 2155500200018 
ENDSUBENT           17          0                                 2155500299999 
ENDENTRY             2          0                                 2155599999999