Crate nuclear

Neutron transport Monte Carlo

Neutron transport Monte Carlo written in Rust, intended for nuclear reactor simulations.

Modules

• diagnostics
  Handles diagnostics functions for tracking neutron behavior over time.
• geometry
  Different part types with material properties through the use of simple constructive solid geometry tools.
• heat_diffusion
  Heat diffusion simulation.
• materials
  Material data and energy-dependent properties for common materials used in nuclear engineering.
• neutrons
  Neutron simulation with scattering, absorption and fission.
• simulation
  Overarching simulation module that integrates the other modules.
• utils
  Utilities for file-handling, vectors etc.