- #1

- 22,095

- 6,742

Broadly, reactor physics calculations involve solving equations related to neutron transport or diffusion in the complex reactor geometry. The calculations are represented by a system of coupled nonlinear partial differential equations, and particularly partial integro-differential equations (or integro-partial-differential equations).

Some methods, e.g., MC or Sn methods are only appropriate for limited applications such as criticality or a time-specific statepoint in a calculation. For depletion calculations, deterministic methods are more appropriate.

https://en.wikipedia.org/wiki/Neutron_transport

https://en.wikipedia.org/wiki/Method_of_characteristics

MIT's OpenMOC Method of Characteristics Code should be of interest -

__https://mit-crpg.github.io/OpenMOC/__

The choice of method depends on application.

I've posted some links to get started, but I plan to elaborate more on the subject.