Cubit 17.10 User Documentation

Importing MCNP Models

MCNP (Monte Carlo N‑Particle) is a general‑purpose radiation transport code that simulates how particles move through matter.

CUBIT can read an MCNP input file and convert its constructive solid geometry — cells, surfaces, and lattices — into an ACIS solid model geometry. This makes it possible to take an existing MCNP model and turn it into CAD geometry that can be cleaned up, meshed, and exported for radiation-transport workflows such as DAGMC. The conversion is based on the open-source mcnp2cad translator that has been converted to use native CUBIT functionality.

The command used to import an MCNP file is:

Import MCNP '<filename>' [verbose] [debug] [debug_output] [debug_input] [extra_effort] [skip_mats] [skip_merge] [skip_imps] [skip_nums] [skip_graveyard] [skip_imprint] [uwuw_names] [tol <value>]

A log of the conversion is always written to a file named mcnp_import.log in the current working directory.

Import Options

By default the importer tags the generated geometry with the information needed by downstream neutronics workflows and cleans up the result by imprinting and merging. The options below, most of which begin with skip_, turn individual steps off.