Crate materials_for_mc

Modules§

Config: Global configuration container for the nuclear data library.
Element: Represents a chemical element identified by its symbol (e.g. "Fe").
Material: Represents a heterogeneous collection of nuclides (or elements expanded to their naturally abundant isotopes) along with the material density and nuclear data needed for transport / analysis.
Materials: Container for many Material instances with shared nuclide caching.
Nuclide: Core data model for a single nuclide and its reaction cross section data.
Reaction: Represents a single reaction channel (identified by ENDF/MT number) for a specific nuclide at a given temperature.