ENTRY            21052   20200930                             22912105200000001 
SUBENT        21052001   20200930                             22912105200100001 
BIB                 11         24                                 2105200100002 
TITLE       The total average cross section for the reactions     2105200100003 
            Ni-58(n,Np)Co-57, Ni-58(n,pn)Co-57 and Ni-58(n,d)Co-572105200100004 
             in a fission type reactor spectrum                   2105200100005 
AUTHOR     (A.Bruggeman,W.Maenhaut,J.Hoste)                       2105200100006 
REFERENCE  (J,RRL,18,87,1974)                                     2105200100007 
INSTITUTE  (2BLGGHT,2BLGMOL)                                      2105200100008 
FACILITY   (REAC,2BLGGHT)                                         2105200100009 
           (REAC,2BLGMOL)                                         2105200100010 
SAMPLE      Analytical grade nickel foils, 12.7 mm in diameter    2105200100011 
            and 0.5 mm thick, for the Gent irradiations and       2105200100012 
            nickel wires of 10 mg for the Mol irradiations.       2105200100013 
            Sodium free aluminum wires as monitors.               2105200100014 
METHOD     (ACTIV)                                                2105200100015 
DETECTOR   (GELI) One calibrated Ge(Li) detector for the monitor  2105200100016 
            reactions and one Ge(Li) detector, 78 cm3 volume and  2105200100017 
            14.2% efficiency, for the Co-57 activity.             2105200100018 
MONITOR    ((MONIT1)13-AL-27(N,A)11-NA-24,,SIG,,FIS)              2105200100019 
           ((MONIT2)28-NI-58(N,P)27-CO-58-G,,SIG,,FIS)            2105200100020 
CORRECTION  For gamma ray attenuation in the sample and for       2105200100021 
            contribution to the cross section from the            2105200100022 
            Ni-58(n,2n)Ni-57(B+)Co-57 reaction.                   2105200100023 
HISTORY    (19790824C) CN.                                        2105200100024 
           (20200930A) SD: Updated to new date formats,lower case.2105200100025 
           Corrections in all Subents.                            2105200100026 
ENDBIB              24          0                                 2105200100027 
COMMON               2          3                                 2105200100028 
MONIT1     MONIT2                                                 2105200100029 
MB         MB                                                     2105200100030 
   0.64       104.                                                2105200100031 
ENDCOMMON            3          0                                 2105200100032 
ENDSUBENT           31          0                                 2105200199999 
SUBENT        21052002   20200930                             22912105200200001 
BIB                  7         10                                 2105200200002 
REACTION   (28-NI-58(N,X)27-CO-57,,SIG,,FIS)                      2105200200003 
INC-SPECT  The U-235 thermal fission neutron spectrum.            2105200200004 
DECAY-DATA (27-CO-57,271.D,DG,122.1,0.85)                         2105200200005 
MISC-COL   (MISC) The quoted error is the statistical error       2105200200006 
            on the mean at a 95% confidence level.                2105200200007 
ERR-ANALYS (ERR-S) Statistical error (derived from the value      2105200200008 
           given in MISC col.)                                    2105200200009 
STATUS     (TABLE) Tbl. 3 from Radioch.Radioanal.Lett.,18(1974)87 2105200200010 
HISTORY    (20200930A) SD: SF3=N+P and D -> X in REACTION code.   2105200200011 
           STATUS updated. EN-DUMMY=1.5 MeV -> KT-DUMMY=1.32 MeV  2105200200012 
ENDBIB              10          0                                 2105200200013 
COMMON               1          3                                 2105200200014 
KT-DUMMY                                                          2105200200015 
MEV                                                               2105200200016 
 1.32                                                             2105200200017 
ENDCOMMON            3          0                                 2105200200018 
DATA                 3          1                                 2105200200019 
DATA       ERR-S      MISC                                        2105200200020 
MB         MB         MB                                          2105200200021 
  0.216      0.0025       0.005                                   2105200200022 
ENDDATA              3          0                                 2105200200023 
ENDSUBENT           22          0                                 2105200299999 
ENDENTRY             2          0                                 2105299999999