ENTRY            11925   19830802                             00001192500000001 
SUBENT        11925001   19830802                             00001192500100001 
BIB                 10         13                                 1192500100002 
INSTITUTE  (1CANCRC)                                              1192500100003 
REFERENCE  (J,NSE,21,20,65)                                       1192500100004 
AUTHOR     (R.WERNER,T.EASTWOOD)                                  1192500100005 
TITLE      THE THERMAL NEUTRON CAPTURE CROSS SECTION AND          1192500100006 
           RESONANCE- CAPTURE INTEGRAL OF RU106.                  1192500100007 
INC-SPECT  REACTOR SPECTRUM                                       1192500100008 
METHOD     (ACTIV) ACTIVATION                                     1192500100009 
DECAY-DATA (45-RH-107,21.85MIN,DG,307.,0.75)                      1192500100010 
MONITOR    (27-CO-59(N,G)27-CO-60,,SIG)                           1192500100011 
           (27-CO-59(N,G)27-CO-60,,RI)                            1192500100012 
STATUS     (SCSRS)                                                1192500100013 
HISTORY    (760802T) TRANSLATED FROM SCISRS                       1192500100014 
           (830802A) CONVERTED TO REACTION FORMALISM              1192500100015 
ENDBIB              13          0                                 1192500100016 
COMMON               2          3                                 1192500100017 
MONIT1     MONIT2                                                 1192500100018 
B          B                                                      1192500100019 
 37.5       72.7                                                  1192500100020 
ENDCOMMON            3          0                                 1192500100021 
ENDSUBENT           20          0                                 1192500199999 
SUBENT        11925002   19830802                             00001192500200001 
BIB                  1          1                                 1192500200002 
REACTION   (44-RU-106(N,G)44-RU-107,,RI)                          1192500200003 
ENDBIB               1          0                                 1192500200004 
NOCOMMON             0          0                                 1192500200005 
DATA                 3          1                                 1192500200006 
EN-MIN     DATA       DATA-ERR                                    1192500200007 
MEV        B          B                                           1192500200008 
 5.     -07 2.0    +00 6.     -01                                 1192500200009 
ENDDATA              3          0                                 1192500200010 
ENDSUBENT            9          0                                 1192500299999 
SUBENT        11925003   19830802                             00001192500300001 
BIB                  1          1                                 1192500300002 
REACTION   (44-RU-106(N,G)44-RU-107,,SIG,,SPA)                    1192500300003 
ENDBIB               1          0                                 1192500300004 
NOCOMMON             0          0                                 1192500300005 
DATA                 2          1                                 1192500300006 
EN-DUMMY   DATA                                                   1192500300007 
MEV        B                                                      1192500300008 
 2.53   -08 1.89   -01                                            1192500300009 
ENDDATA              3          0                                 1192500300010 
ENDSUBENT            9          0                                 1192500399999 
SUBENT        11925004   19830802                             00001192500400001 
BIB                  3          4                                 1192500400002 
REACTION   (44-RU-106(N,G)44-RU-107,,SIG,,MXW)                    1192500400003 
STATUS     (DEP,11925003)                                         1192500400004 
ANALYSIS   CALCULATED FROM REACTOR SPECTRUM VALUE, USING          1192500400005 
            S(0)=15+-1.                                           1192500400006 
ENDBIB               4          0                                 1192500400007 
NOCOMMON             0          0                                 1192500400008 
DATA                 3          1                                 1192500400009 
EN-DUMMY   DATA       DATA-ERR                                    1192500400010 
MEV        B          B                                           1192500400011 
 2.53   -08 1.46   -01 4.5    -02                                 1192500400012 
ENDDATA              3          0                                 1192500400013 
ENDSUBENT           12          0                                 1192500499999 
ENDENTRY             4          0                                 1192599999999