I need to import the results of a simulation in fluka and use them as a source for an openmc simulation. I have used openmc.stats.Tabular to do this, and I was hoping to do a quick simulation to confirm that I have converted between fluka and openmc correctly by measuring the spectrum of my source. However I am not getting any results.
So my first question is: is it possible to use filters and tallies to measure your source spectrum, or are they only able to measure secondary particles?
If the answer is yes, then my next question is what am I doing wrong? Description of what I’m doing below.
I have set up a small uranium sphere (radius 5cm) with a weak point source at the center. I am not interested in the reactions here but when I didn’t do this I got an error because there were no nuclear reactions. Then I have a very thick shell of boron (R=100cm) around the uranium to absorb any neutrons coming from that. Then on the outside the boron I have a detection sphere (R=100 just to check that nothing is getting out of the boron. Then I have a source sphere (R=101), and then I have another detection sphere outside of the source (R=102) to measure the source spectrum. However both detection spheres are measuring zero. My jupyter notebook is attached.
Thanks for any help.
source_check.ipynb (83.4 KB)