Dear fluka experts:
Can the reaction counts such as fission counts be obtained throught using usrtract card,
in mcnp the reaction counts can be obtained throught F4 card,for example,the fission counts
can be obtained like this:
F4:n cell number
fm4 -v material number -6(total fission cross-section)
thanks!
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Received on Wed Aug 07 2019 - 13:13:12 CEST