Some Monte Carlo tools

Tool for converting MCNP input files to OpenMC classes/XML

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

Workflow and Template Toolkit for Simulation (WATTS)

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

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

a companion for writing MCNP input decks

The package for reading mcnp input in a pythonic way

Tool to convert MCNP geometries into TRIPOLI-4 geometries.

Python tools for MCNP

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

Tools used for MCNP input deck syntax highlighting

MCNP SDEF to OpenMC conversion tool

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

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

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

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

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

Convert a GDML geometry to an MCNP card

Recolor your radiant inputs for MCNP model renders.