mcnp   version 6     ld=02/20/18  probid =  11/23/21 11:35:23 
 CUBE TEST
 Number of histories used for normalizing tallies =             1.00

 Mesh Tally Number       124
 neutron  mesh tally.

 Tally bin boundaries:
    X direction:    -50.00      0.00     50.00
    Y direction:    -50.00      0.00     50.00
    Z direction:    -50.00     50.00
    Energy bin boundaries: 0.00E+00 1.00E+36

        X         Y         Z     Result     Rel Error     Volume    Rslt * Vol
    -25.000   -25.000     0.000 1           0.00000E+00 2.50000E+05 2.50000E+05
     25.000   -25.000     0.000 4           0.00000E+00 2.50000E+05 1.00000E+06
    -25.000    25.000     0.000 9           0.00000E+00 2.50000E+05 2.25000E+06
     25.000    25.000     0.000 16          0.00000E+00 2.50000E+05 4.00000E+06
