Missing nuclide in low energy neutron library

[lorenzo.mercolli]

Dear @pattarapol.13

Some low-energy neutron cross sections are implemented only for the natural isotopic composition of the material, i.e. FLUKA will give you an error if you choose a single isotope (see comment in this post). You might get lucky if you use simply use the predefined materials.

@pattarapol.13

1.simulate my problem to high energy neutron (>20 MeV) like calculate the recoil as mentioned in this lecture https://www.fluka.org/free_download/course/portugal2010/Lectures/AdvancedMaterial2010.pdf
but I’m not sure how to do it and I don’t know it will give the expected result or not?

You can implement this workaround with the PART-THR card or you can discard neutrons all together with the DISCARD card if they are not relevant for your problem.

@pattarapol.13

2.add another library by converting the ENDF file to group-wise cross-section to FLUKA (I don’t know is it available or not?)

I believe that it is not possible to change or choose the low-energy neutron library in FLUKA (see also this post), but maybe someone from the developer team might give you some more details about that.

Best,
lornezo