ENTRY            14526   20190329                             14491452600000001 
SUBENT        14526001   20190329                             14491452600100001 
BIB                  6          7                                 1452600100002 
TITLE      The Thermal-Neutron Fission Cross Section of Pu240     1452600100003 
AUTHOR     (C.B.Bigham)                                           1452600100004 
REFERENCE  (J,CJP,36,503,1958)                                    1452600100005 
           #doi:10.1139/p58-051                                   1452600100006 
INSTITUTE  (1CANCRC)                                              1452600100007 
FACILITY   (REAC,1CANCRC) The NRX nuclear reactor at Chalk River. 1452600100008 
HISTORY    (20190329C) BP                                         1452600100009 
ENDBIB               7          0                                 1452600100010 
COMMON               1          3                                 1452600100011 
EN-DUMMY                                                          1452600100012 
EV                                                                1452600100013 
     0.0253                                                       1452600100014 
ENDCOMMON            3          0                                 1452600100015 
ENDSUBENT           14          0                                 1452600199999 
SUBENT        14526002   20190329                             14491452600200001 
BIB                  6         35                                 1452600200002 
REACTION   ((94-PU-240(N,F),,SIG,,SPA)/(94-PU-239(N,F),,SIG,,SPA))1452600200003 
SAMPLE     Plutonium samples 2 in. in diameter were cut from      1452600200004 
           large 0.016 in. aluminum sheets that had been          1452600200005 
           uniformly coated with several layers of lacquer        1452600200006 
            (cellulose nitrate dissolved in amyl acetate)         1452600200007 
           containing plutonium nitrate dissolved in acetone.     1452600200008 
           240Pu sample:                                          1452600200009 
           (94-PU-240,ENR=0.89365)                                1452600200010 
           (94-PU-239,ENR=0.10131)                                1452600200011 
           (94-PU-241,ENR=0.00483)                                1452600200012 
           (94-PU-242,ENR=0.00018)                                1452600200013 
           239Pu sample:                                          1452600200014 
           (94-PU-239,ENR=0.97884)                                1452600200015 
           (94-PU-240,ENR=0.02043)                                1452600200016 
           (94-PU-241,ENR=0.00073)                                1452600200017 
DETECTOR   (FISCH) The samples were mounted on either side of a   1452600200018 
           thin aluminum partition in the common cathode of a     1452600200019 
           back-to-back gridded ion chamber. For the fission      1452600200020 
           counting the chamber was operated at low pressure to   1452600200021 
           permit complete discrimination between fission and     1452600200022 
           alpha pulses.                                          1452600200023 
METHOD     (RVAL,CHSEP) If isotopically pure samples of Pu239     1452600200024 
           and Pu240 are available, the ratio of the              1452600200025 
           alpha-disintegration rates and the published ratio of  1452600200026 
           the alpha-decay half-lives would give the ratio of     1452600200027 
           the masses of the samples. The ratio of the fission    1452600200028 
           rates in these samples, when irradiated in the same    1452600200029 
           neutron flux, would then give the ratio of the         1452600200030 
           fission cross sections. The accuracy would be limited  1452600200031 
           to the accuracy with which the ratio of the            1452600200032 
           alpha-decay half-lives is known.                       1452600200033 
ERR-ANALYS (DATA-ERR) Statistical errors arising from the ratio   1452600200034 
           measurements, decay constant ratio errors,             1452600200035 
           mass-spectrometer analyses.                            1452600200036 
STATUS     (TABLE) page 506.                                      1452600200037 
ENDBIB              35          0                                 1452600200038 
NOCOMMON             0          0                                 1452600200039 
DATA                 2          1                                 1452600200040 
DATA       DATA-ERR                                               1452600200041 
NO-DIM     NO-DIM                                                 1452600200042 
   -9.3E-04    7.7E-04                                            1452600200043 
ENDDATA              3          0                                 1452600200044 
ENDSUBENT           43          0                                 1452600299999 
SUBENT        14526003   20190329                             14491452600300001 
BIB                  5          6                                 1452600300002 
REACTION   (94-PU-240(N,F),,SIG,,SPA)                             1452600300003 
MONITOR    (94-PU-239(N,F),,SIG,,SPA)                             1452600300004 
MONIT-REF  ((MONIT),D.J.Hughes+,P,BNL-325,1955)                   1452600300005 
ERR-ANALYS (DATA-ERR) No details on sources of uncertainties.     1452600300006 
STATUS     (DEP,14526002)                                         1452600300007 
           (TABLE) page 506.                                      1452600300008 
ENDBIB               6          0                                 1452600300009 
COMMON               2          3                                 1452600300010 
MONIT      MONIT-ERR                                              1452600300011 
B          B                                                      1452600300012 
      900.0       40.0                                            1452600300013 
ENDCOMMON            3          0                                 1452600300014 
DATA                 2          1                                 1452600300015 
DATA       DATA-ERR                                               1452600300016 
B          B                                                      1452600300017 
       -0.8        0.7                                            1452600300018 
ENDDATA              3          0                                 1452600300019 
ENDSUBENT           18          0                                 1452600399999 
ENDENTRY             3          0                                 1452699999999