A python library to allow ease of data reduction and data viewing for MCNP output file

Thermal Hydraulic Sub-Channel Code for an Average Rod (Using MCNP for input values)

Convert a GDML geometry to an MCNP card

a companion for writing MCNP input decks

A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak

an unofficial MCNP input file generator

Tally table is a simple GUI program which extracts user defined tallies from a MCNP output.

The package for reading mcnp input in a pythonic way

Tool to rename cells, surfaces, materials and universes in MCNP input files.

Recolor your radiant inputs for MCNP model renders.

Tools used for MCNP input deck syntax highlighting

Workflow and Template Toolkit for Simulation (WATTS)

notepad++ plugin for MCNP deck development. shows informative popups for selected cell/surface/physics cards. Inbuilt error checking.

A tool for making reproducible materials and standardizing use across several neutronics codes

Tool to convert MCNP geometries into TRIPOLI-4 geometries.

Transfer meta information on cells from an STP file to MCNP model. Set materials and densities according to tags specified in STP model tree.

Tool for converting MCNP input files to OpenMC classes/XML

Some Monte Carlo tools

MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.

Python tools for MCNP