GEANT-CALOR INTERFACE V 1.05/04 Output File
                  ===========================================

        GEANT Material Parameters                MICAP Material Parameters
        -------------------------                -------------------------
 Material                No/Iso    A     Z  |    A     Z   Density   Coll.Len
--------------------------------------------+---------------------------------
 Air.................     1/ 1   14.0    7  |  14.0    7  0.4040E-04 0.106E+05
                          1/ 2   16.0    8  |  16.0    8  0.9524E-05 0.128E+05
                          1/ 3   40.0   18  |  39.9   18  0.1816E-06 0.259E+07
 Lead................     2/ 1  207.2   82  | 207.2   82  0.3299E-01 0.691E+01
 Iron................     3/ 1   55.8   26  |  55.8   26  0.8486E-01 0.228E+01
 mixtureForDCH.......     4/ 1   39.9   18  |  39.9   18  0.1226E-04 0.383E+05
                          4/ 2   12.0    6  |  12.0    6  0.2783E-05 0.138E+06
                          4/ 3   16.0    8  |  16.0    8  0.5567E-05 0.219E+05
 Aluminum............     5/ 1   27.0   13  |  27.0   13  0.6027E-01 0.701E+01
 Mylar...............     6/ 1   12.0    6  |  12.0    6  0.4378E-01 0.875E+01
                          6/ 2    1.0    1  |   1.0    1  0.3502E-01 0.659E+01
                          6/ 3   16.0    8  |  16.0    8  0.1751E-01 0.695E+01
 HeliumGas...........     7/ 1    4.0    2  |   4.0    2  0.1882E-04 0.757E+04
 BC408...............     8/ 1    1.0    1  |   1.0    1  0.3206E+00 0.720E+00
                          8/ 2   12.0    6  |  12.0    6  0.2484E-01 0.154E+02
------------------------------------------------------------------------------
                                                Density in (Atoms/barn/cm)
                                    Collision Length for 1 MeV neutron in (cm)


                    USED NEUTRON CROSS-SECTION FILES
                    --------------------------------

 File      : /data.local1/fairsoft/transport/geant3/data/xsneut.dat            
 Generated : Wed Nov 24 16:18:19 1999
 Comment   : MICAP neutron cross-section file. TOL=2.0% ANG=2.0%   C.Zeitnitz  


 MICAP :    418360 words used in GCBANK for neutron x-section tables