Reading MT=444 in openmc

User Support
1

Hello all,

I plan to use openmc to output point-wise mt=444 cross section.
Has openmc already supported that? Where can I set MT number?
If not, is it possible to add several lines into source code to realize the function?

Thanks!
Jilang

2

PyNE would be a better suited tool for printing out ACE cross section data, but if you really wanted to do it from within OpenMC, go to the read_reactions subroutine in ace.F90 and add the following after the line that reads ‘rxn % sigma = get_real(NE)’:

if (rxn % MT == 444) then
do j = 1, NE
write (40,*) nuc % energy(j), rxn % sigma(j)
end do
end if

Note that you’ll need to declare j. This will give you energy, cross section pairs in fort.40.