The question of neutronics or reactor physics methods has come up at various times and with respect to different aspects. I thought it would be worthwhile to explore various methods, the technology and their applications.(adsbygoogle = window.adsbygoogle || []).push({});

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.

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# Computational Methods for Reactor Physics (Core Simulation)

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