Hello, I am trying to create a custom cross section file at high temperatures (900K and 959K) for both thermal scattering data and incident neutron data for graphite, FLiBe, and U235. I’m not sure how to go about doing this or if what I was doing is correct? I believe I have code which makes the necessary .h5 files for uranium, but I don’t know how to do the same for thermal scattering with graphite at 900K:
Here is the uranium:
Also when actually using these files in simulations, do you still need to define the temperature of the material? Or can I just register the cross section file “as is” and just run it?
Thank you!