ENTRY            11906   19831109                             00001190600000001 
SUBENT        11906001   19831109                             00001190600100001 
BIB                  9         12                                 1190600100002 
INSTITUTE  (1USAORL)                                              1190600100003 
REFERENCE  (P,ORNL-3832,6,6509)                                   1190600100004 
AUTHOR     (P.M.LANTZ)                                            1190600100005 
TITLE      THERMAL-NEUTRON CROSS SECTION AND RESONANCE INTEGRAL   1190600100006 
            OF RU-102.                                            1190600100007 
INC-SPECT  REACTOR SPECTRUM                                       1190600100008 
METHOD     (ACTIV) ACTIVATION                                     1190600100009 
DECAY-DATA (44-RU-103,40.D,DG,498.,0.90)                          1190600100010 
MONITOR    (27-CO-59(N,G)27-CO-60,,SIG)                           1190600100011 
           (79-AU-197(N,G)79-AU-198,,SIG)                         1190600100012 
HISTORY    (770509C)                                              1190600100013 
           (831109A) CONVERTED TO REACTION FORMALISM              1190600100014 
ENDBIB              12          0                                 1190600100015 
NOCOMMON             0          0                                 1190600100016 
ENDSUBENT           15          0                                 1190600199999 
SUBENT        11906002   19831109                             00001190600200001 
BIB                  2          3                                 1190600200002 
REACTION   (44-RU-102(N,G)44-RU-103,,SIG,,MXW)                    1190600200003 
ANALYSIS   AVERAGE OF VALUES CALCULATED FROM 2 MEASUREMENTS IN    1190600200004 
            REACTOR SPECTRUM                                      1190600200005 
ENDBIB               3          0                                 1190600200006 
NOCOMMON             0          0                                 1190600200007 
DATA                 3          1                                 1190600200008 
EN-DUMMY   DATA       DATA-ERR                                    1190600200009 
EV         B          PER-CENT                                    1190600200010 
 0.0253     1.23       10.                                        1190600200011 
ENDDATA              3          0                                 1190600200012 
ENDSUBENT           11          0                                 1190600299999 
SUBENT        11906003   19831109                             00001190600300001 
BIB                  2          3                                 1190600300002 
REACTION   (44-RU-102(N,G)44-RU-103,,RI)                          1190600300003 
ANALYSIS   AVERAGE OF VALUES CALCULATED FROM 2 MEASUREMENTS IN    1190600300004 
            REACTOR SPECTRUM                                      1190600300005 
ENDBIB               3          0                                 1190600300006 
NOCOMMON             0          0                                 1190600300007 
DATA                 3          1                                 1190600300008 
EN-MIN     DATA       DATA-ERR                                    1190600300009 
EV         B          PER-CENT                                    1190600300010 
 0.54       4.14       10.                                        1190600300011 
ENDDATA              3          0                                 1190600300012 
ENDSUBENT           11          0                                 1190600399999 
ENDENTRY             3          0                                 1190699999999