ENTRY            10604   20040726                             00001060400000001 
SUBENT        10604001   20040726                             00001060400100001 
BIB                 11         15                                 1060400100002 
INSTITUTE  (1CANCRC)                                              1060400100003 
REFERENCE  (P,AECL-4259,12,197208)                                1060400100004 
AUTHOR     (D.C.Santry,R.D.Werner)                                1060400100005 
TITLE      Thermal Neutron (n,alpha) Reactions.                   1060400100006 
FACILITY   (REAC,1CANCRC) NRU reactor.                            1060400100007 
METHOD     (ACTIV) Activation analysis                            1060400100008 
MONITOR    No information                                         1060400100009 
ERR-ANALYS No information on uncertainty.                         1060400100010 
COMMENT    Results indicated that the 55Mn content was no greater 1060400100011 
            in the irradiated 58Co-Al samples than the natural Mn 1060400100012 
            content of the high purity Al foils.                  1060400100013 
STATUS     (APRVD) Approved by author 1976/6/15.                  1060400100014 
HISTORY    (19760504C)                                            1060400100015 
           (19831017A) Converted to REACTION formalism            1060400100016 
           (20040726A) Converted to new date formats, lower case. 1060400100017 
ENDBIB              15          0                                 1060400100018 
NOCOMMON             0          0                                 1060400100019 
ENDSUBENT           18          0                                 1060400199999 
SUBENT        10604002   20040726                             00001060400200001 
BIB                  1          1                                 1060400200002 
REACTION   (27-CO-58(N,A)25-MN-55,,SIG,,MXW)                      1060400200003 
ENDBIB               1          0                                 1060400200004 
NOCOMMON             0          0                                 1060400200005 
DATA                 2          1                                 1060400200006 
EN-DUMMY   DATA-MAX                                               1060400200007 
EV         MB                                                     1060400200008 
0.0253      3.                                                    1060400200009 
ENDDATA              3          0                                 1060400200010 
ENDSUBENT            9          0                                 1060400299999 
ENDENTRY             2          0                                 1060499999999