ENTRY            11990   20181102                             14441199000000001 
SUBENT        11990001   20181102                             14441199000100001 
BIB                  7         10                                 1199000100002 
INSTITUTE  (1CANCRC)                                              1199000100003 
REFERENCE  (J,CJP,44,2956,1966)                                   1199000100004 
AUTHOR     (R.Courtemanche,T.A.Eastwood,R.D.Werner)               1199000100005 
TITLE      The reactor neutron capture cross section of Sb124.    1199000100006 
FACILITY   (REAC,1CANCRC)                                         1199000100007 
STATUS     (TABLE) p.2958 of Can.J.Phys.44,2956(1966)             1199000100008 
HISTORY    (19760802T) Translated from SCISRS                     1199000100009 
           (19830802A) Converted to reaction formalism            1199000100010 
           (20181031U) OS. Minor BIB corr., converted to lower and1199000100011 
            upper case.                                           1199000100012 
ENDBIB              10          0                                 1199000100013 
NOCOMMON             0          0                                 1199000100014 
ENDSUBENT           13          0                                 1199000199999 
SUBENT        11990002   20181102                             14441199000200001 
BIB                  6          9                                 1199000200002 
REACTION   (51-SB-124(N,G)51-SB-125,,SIG,,SPA)                    1199000200003 
SAMPLE     Natural samples, each containing about 5 mg Sb         1199000200004 
METHOD     (ACTIV) Data value given is average of values obtained 1199000200005 
            from the Sb-125/Sb-124 activity ratio and from        1199000200006 
            measurements on Te-125-M daughter.                    1199000200007 
DECAY-DATA (51-SB-125,2.75YR,DG)                                  1199000200008 
           (51-SB-124,60.4D,DG)                                   1199000200009 
ERR-ANALYS (DATA-ERR) No information on sources of uncertainty    1199000200010 
INC-SPECT   Reactor spectrum                                      1199000200011 
ENDBIB               9          0                                 1199000200012 
NOCOMMON             0          0                                 1199000200013 
DATA                 3          1                                 1199000200014 
EN-DUMMY   DATA       DATA-ERR                                    1199000200015 
MEV        B          B                                           1199000200016 
 2.53   -08 6.5    +00 1.5    +00                                 1199000200017 
ENDDATA              3          0                                 1199000200018 
ENDSUBENT           17          0                                 1199000299999 
ENDENTRY             2          0                                 1199099999999