API Reference

Low-level Interface

Material

ENDF material with multiple files/sections

get_materials

Return a list of all materials within an ENDF file.

High-level Interface

IncidentNeutron	Continuous-energy neutron interaction data.
Tabulated1D	A one-dimensional tabulated function.
Reaction	A nuclear reaction
Product	Secondary particle emitted in a nuclear reaction

ACE File Interface

ace.Table	ACE cross section table
ace.TableType	Type of ACE data table.

ace.get_table	Read a single table from an ACE file
ace.get_tables	Get all tables from an ACE-formatted file.
ace.get_libraries_from_xsdir	Determine paths to ACE files from an MCNP xsdir file.