ENTRY            11892   19830919                             00001189200000001 
SUBENT        11892001   19830919                             00001189200100001 
BIB                  9         11                                 1189200100002 
INSTITUTE  (1USAORL)                                              1189200100003 
REFERENCE  (P,ORNL-3832,5,6509)                                   1189200100004 
AUTHOR     (J.HALPERIN,R.E.DRUSCHEL)                              1189200100005 
TITLE      THE THERMAL-NEUTRON CAPTURE CROSS SECTION AND RESONANCE1189200100006 
            INTEGRAL OF RU-96.                                    1189200100007 
INC-SPECT  REACTOR SPECTRUM                                       1189200100008 
METHOD     (ACTIV) ACTIVATION                                     1189200100009 
DECAY-DATA (44-RU-97,2.88D,DG,216.,0.90)                          1189200100010 
MONITOR    (25-MN-55(N,G)25-MN-56,,SIG)                           1189200100011 
HISTORY    (770509C)                                              1189200100012 
           (830919A) CONVERTED TO REACTION FORMALISM              1189200100013 
ENDBIB              11          0                                 1189200100014 
NOCOMMON             0          0                                 1189200100015 
ENDSUBENT           14          0                                 1189200199999 
SUBENT        11892002   19830919                             00001189200200001 
BIB                  2          3                                 1189200200002 
REACTION   (44-RU-96(N,G)44-RU-97,,SIG,,MXW)                      1189200200003 
ANALYSIS   AVERAGE OF VALUES CALCULATED FROM 2 MEASUREMENTS IN    1189200200004 
            REACTOR SPECTRUM.                                     1189200200005 
ENDBIB               3          0                                 1189200200006 
NOCOMMON             0          0                                 1189200200007 
DATA                 3          1                                 1189200200008 
EN-DUMMY   DATA       DATA-ERR                                    1189200200009 
EV         B          PER-CENT                                    1189200200010 
 0.0253     0.271      10.                                        1189200200011 
ENDDATA              3          0                                 1189200200012 
ENDSUBENT           11          0                                 1189200299999 
SUBENT        11892003   19830919                             00001189200300001 
BIB                  2          3                                 1189200300002 
REACTION   (44-RU-96(N,G)44-RU-97,,RI)                            1189200300003 
ANALYSIS   AVERAGE OF VALUES CALCULATED FROM 2 MEASUREMENTS IN    1189200300004 
            REACTOR SPECTRUM.                                     1189200300005 
ENDBIB               3          0                                 1189200300006 
NOCOMMON             0          0                                 1189200300007 
DATA                 3          1                                 1189200300008 
EN-MIN     DATA       DATA-ERR                                    1189200300009 
EV         B          PER-CENT                                    1189200300010 
 0.54       5.51       7.                                         1189200300011 
ENDDATA              3          0                                 1189200300012 
ENDSUBENT           11          0                                 1189200399999 
ENDENTRY             3          0                                 1189299999999