Hi I have a question about openmc.Source
I have a complex geometry and define a source: openmcSource(domains=[somematerial]).
I was wondering when it says that neutrons are rejected if they are not in the given domain. Do you resample them until they are all in the domain, or do you just run with the remaining neutrons.
If it is the former then the rest of the question is no longer a problem.
Now if you don’t resample then:
lets say 100 neutrons are placed and 52 were transported, and 48 rejected because not in domain. Do you renormalise with respect to all the neutrons placed (so 100) or do you renormalize over only the 52 transported (not rejected).
If you renormalise with only the transported ones, 52, then no problem nothing changes it just reduces the quality of the statistics.
If you renormalise with respect to the 100 placed but 48 were rejected, then a correction factor of V_source/V_tot would be necessary to get the absolut flux (if we use uniforme distribution)?
I hope this is clear let me know if you want some clarification
Thanks for the help
JB