ENTRY            14525   20190329                             14491452500000001 
SUBENT        14525001   20190329                             14491452500100001 
BIB                 11         28                                 1452500100002 
TITLE      Pile Neutron Capture Cross Section of 33 Hr. Ce143     1452500100003 
AUTHOR     (L.P.Roy,L.Yaffe)                                      1452500100004 
REFERENCE  (J,CJC,34,238,1956)                                    1452500100005 
           #doi:10.1139/v56-036                                   1452500100006 
INSTITUTE  (1CANMCG)                                              1452500100007 
FACILITY   (REAC,1CANCRC) The NRX nuclear reactor at Chalk River. 1452500100008 
DETECTOR   (GEMUC) The counter was the "end window" type with a   1452500100009 
           mica window of mass 2.3 mgm./cm2.                      1452500100010 
METHOD     (ACTIV,CHSEP) Spectroscopically pure samples of        1452500100011 
           cerium oxide, sealed in small quartz ampoules, were    1452500100012 
           irradiated in the NRX nuclear reactor at different     1452500100013 
           neutron fluxes for different times. After irradiation, 1452500100014 
           the cerium oxide was removed from the quartz ampoule   1452500100015 
           and chemically separated. The final hydroxide          1452500100016 
           precipitate was transferred as a slurry to an          1452500100017 
           aluminum tray, where it was spread evenly, dried, and  1452500100018 
           the counting-rate determined by a Geiger-Miiller       1452500100019 
           counter. The pile neutron capture cross section of     1452500100020 
           the 33 hr. Ce143 was determined by separating Pr144,   1452500100021 
           the daughter of Ce144, from the rigorously-purified    1452500100022 
           cerium at frequent intervals. The amount of Pr144      1452500100023 
           formed increased linearly with the square of the       1452500100024 
           neutron flux in a manner consistent with that of a     1452500100025 
           successive neutron capture reaction.                   1452500100026 
MONITOR    (58-CE-142(N,G)58-CE-143,,SIG)                         1452500100027 
MONIT-REF  ((MONIT)12051001,L.P.Roy+,J,CJC,34,1023,1956)          1452500100028 
DECAY-DATA (58-CE-143,33.0HR,B-)                                  1452500100029 
HISTORY    (20190329C)  BP                                        1452500100030 
ENDBIB              28          0                                 1452500100031 
COMMON               2          3                                 1452500100032 
MONIT      EN-DUMMY                                               1452500100033 
B          EV                                                     1452500100034 
       0.95     0.0253                                            1452500100035 
ENDCOMMON            3          0                                 1452500100036 
ENDSUBENT           35          0                                 1452500199999 
SUBENT        14525002   20190329                             14491452500200001 
BIB                  3          3                                 1452500200002 
REACTION   (58-CE-143(N,G)58-CE-144,,SIG,,SPA)                    1452500200003 
ERR-ANALYS (DATA-ERR) No information on sources of uncertainties. 1452500200004 
STATUS     (TABLE) page 243.                                      1452500200005 
ENDBIB               3          0                                 1452500200006 
NOCOMMON             0          0                                 1452500200007 
DATA                 2          1                                 1452500200008 
DATA       DATA-ERR                                               1452500200009 
B          B                                                      1452500200010 
        6.0        0.7                                            1452500200011 
ENDDATA              3          0                                 1452500200012 
ENDSUBENT           11          0                                 1452500299999 
ENDENTRY             2          0                                 1452599999999