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In many practical applications, it is important to know the total
production of protons (hydrogen), alphas (helium), and other light
charged particles resulting from the neutron flux. Therefore, it
is convenient to have a set of special "gas production" or
"charged-particle production" cross sections that can be used in
application codes. The ENDF format provides a set of MT numbers
for these quantities, but only a few evaluators have added them to
their files:
- MT=203 -- total proton production
- MT=204 -- total deuteron production
- MT=205 -- total triton production
- MT=206 -- total He-3 production
- MT=207 -- total alpha production
The GASPR module goes through all of the reactions given in an
ENDF-format evaluation, determines which charged particles would
be produced by the reaction, and adds up the particle yield times
the reaction cross section to produce the desired gas production
cross sections. It uses data from an input ENDF tape and an
input PENDF tape, and it writes the results on an output PENDF
tape. They are then available for plotting, multigroup averaging,
or reformatting for the MCNP Monte Carlo code.
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