ENTRY            13130   20181203                             144513130  0    1 
SUBENT        13130001   20181203                             144513130  1    1 
BIB                 15         39                                 13130  1    2 
INSTITUTE  (1USALAS)                                              13130  1    3 
REFERENCE  (J,PR/C,36,1896,1987)                                  13130  1    4 
AUTHOR     (W.L.Talbert Jr,J.W.Starner,R.J.Estep,S.J.Balestrini,  13130  1    5 
           M.Attrep Jr,D.W.Efurd,F.R.Roensch)                     13130  1    6 
TITLE      Thermal-neutron fission cross section of 26.1-min      13130  1    7 
           U-235M                                                 13130  1    8 
FACILITY   (REAC,1USALAS) Los Alamos Omega West Reactor           13130  1    9 
INC-SOURCE (THCOL)                                                13130  1   10 
INC-SPECT  Peak energy of Maxwellian normal energy distribution   13130  1   11 
            is 26 milli-eV, the energy of the most probable flux  13130  1   12 
            in the wavelength representation of the Maxwellian    13130  1   13 
            flux is 75.5 milli-eV.                                13130  1   14 
           The neutron spectrum is approximated by a Maxwellian   13130  1   15 
            distribution of temperature 350 deg-K.                13130  1   16 
SAMPLE     6.E+10 to 3.E+11 atoms deposited on 9.5-mm diameter    13130  1   17 
            platinum disk. Samples obtained by chemical separation13130  1   18 
            of uranium grown in a 15-min period by alpha decay    13130  1   19 
            of plutonium solution (200-400 mg Pu).                13130  1   20 
DETECTOR   (FISCH)                                                13130  1   21 
DECAY-DATA (92-U-235-M,26.1MIN)                                   13130  1   22 
ANALYSIS   Multiscale spectrum fitted to a + b x exp(-lambda T)   13130  1   23 
           where a is normalized fission rate for 235-U-g in the  13130  1   24 
                   deposit at long times after separation,        13130  1   25 
                   including background and possible fissions     13130  1   26 
                   from plutonium                                 13130  1   27 
                 B is related to ratio of the isomeric to the     13130  1   28 
                   ground state cross sections                    13130  1   29 
                 T is the time elapsed since the end of the       13130  1   30 
                   grow-in period during chemical separation      13130  1   31 
            lambda is the isomeric state decay constant, 0.02656  13130  1   32 
                   minutes(-1).                                   13130  1   33 
CORRECTION Correction made for fissions due to any plutonium      13130  1   34 
            found in the deposit by later alpha counting the disk.13130  1   35 
ERR-ANALYS Uncertainty is one standard deviation of the eight     13130  1   36 
            individual samples results                            13130  1   37 
STATUS     (APRVD) W.L.Talbert, 88/10/28                          13130  1   38 
HISTORY    (19880413C)                                            13130  1   39 
           (20181130U) OS. Minor correction in AUTHOR, converted  13130  1   40 
            to lower and upper case.                              13130  1   41 
ENDBIB              39          0                                 13130  1   42 
NOCOMMON             0          0                                 13130  1   43 
ENDSUBENT           42          0                                 13130  199999 
SUBENT        13130002   19881221                             00001313000200001 
BIB                  1          1                                 1313000200002 
REACTION   ((92-U-235-M(N,F),,SIG,,MXW)/(92-U-235(N,F),,SIG,,MXW))1313000200003 
ENDBIB               1          0                                 1313000200004 
NOCOMMON             0          0                                 1313000200005 
DATA                 3          1                                 1313000200006 
EN-MEAN    DATA       DATA-ERR                                    1313000200007 
MILLI-EV   NO-DIM     NO-DIM                                      1313000200008 
 26.        1.42       0.04                                       1313000200009 
ENDDATA              3          0                                 1313000200010 
ENDSUBENT            9          0                                 1313000299999 
ENDENTRY             2          0                                 1313099999999