hello everyone,
Recently I am trying to run a simulation with Triso particles and want to calculate the multiplication factor but I had a problem defying the initial neutron source. I tried to insert a point source at specific place in the geometry and state.Box source all over the core volume but from the mesh plots of fission and flux distribution I can see that a lot of places in my geometry doesn’t feel neutron and in every calculation I get different places feeling the flux not the whole geometry.
i’d love to get some suggestion how to maintain my source.
thanks
When you’re running a k-eigenvalue calculation, the initial neutron source is arbitrary and will be iterated on until the source distribution reaches a converged state (at which point active batches can begin and tallies can be accumulated). In general, it would be better to start with a box source that covers your geometry rather than a point source (which will likely take more batches to converge). However, it sounds like the real issue in your case is perhaps not simulated enough neutrons / active batches, which may lead to poorly converged tally results. The first thing I would try in your case is to increase the number of neutrons per generation and the number of active batches and see if that helps.