ENTRY            23811   20210616                             23012381100000001 
SUBENT        23811001   20210616                             23012381100100001 
BIB                  7         13                                 2381100100002 
TITLE       Search for A=60 fragments from neutron induced fission2381100100003 
AUTHOR     (A.Elhardt,T.Fastermann,K.Knie,G.Korschinek,G.Rugel,   2381100100004 
           C.Lierse,A.Stippschild)                                2381100100005 
REFERENCE  (R,BLM-JB-1997,49,1998)                                2381100100006 
INSTITUTE  (2GERMUN)                                              2381100100007 
FACILITY   (REAC,2GERMUN) FRM reactor                             2381100100008 
HISTORY    (20210616C)  M.M.                                      2381100100009 
COMMENT     Of authors.                                           2381100100010 
            Fe-59 capture cross-section was measured to take it's 2381100100011 
           contribution in U-235(N,F)Fe-60 fission yield (FY upper2381100100012 
           limit was determined to be 1.E-10, what was derived    2381100100013 
           from measured (2.0+-0.5)*10))-10 value of Fe60/Fe      2381100100014 
           concentration, produced in reactor plant fuel).        2381100100015 
ENDBIB              13          0                                 2381100100016 
COMMON               1          3                                 2381100100017 
EN-DUMMY                                                          2381100100018 
EV                                                                2381100100019 
 0.0253                                                           2381100100020 
ENDCOMMON            3          0                                 2381100100021 
ENDSUBENT           20          0                                 2381100199999 
SUBENT        23811002   20210616                             23012381100200001 
BIB                  7         14                                 2381100200002 
REACTION   (26-FE-59(N,G)26-FE-60,,SIG,,SPA)                      2381100200003 
INC-SOURCE (REAC)                                                 2381100200004 
INC-SPECT   FRM reactor spectrum.                                 2381100200005 
           Neutron flux 1.9E+13 /cm2/sec was determined from Fe-592381100200006 
           activity.                                              2381100200007 
SAMPLE     1.07 mg of iron enriched to 58.4 % in Fe-58.           2381100200008 
METHOD      Fe-59 capture cross section was determined via double 2381100200009 
           neutron capture on Fe-58.                              2381100200010 
           Irradiation time 24 hr in FRM reactor.                 2381100200011 
           Measured concentration of Fe-60/Fe-58                  2381100200012 
            (1.0+-0.2)*10**-11.                                   2381100200013 
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 2381100200014 
           article.                                               2381100200015 
STATUS     (TABLE) Text page 49 of BLM-JB-1997,p.49,1998          2381100200016 
ENDBIB              14          0                                 2381100200017 
NOCOMMON             0          0                                 2381100200018 
DATA                 2          1                                 2381100200019 
DATA       DATA-ERR                                               2381100200020 
B          B                                                      2381100200021 
   7.0      1.4                                                   2381100200022 
ENDDATA              3          0                                 2381100200023 
ENDSUBENT           22          0                                 2381100299999 
ENDENTRY             2          0                                 2381199999999