https://github.com/lanl/mcnptools

mcnp mcnp6

Last synced: 12 Apr 2025

https://github.com/openmc-dev/openmc_mcnp_adapter

Tool for converting MCNP input files to OpenMC classes/XML

mcnp monte-carlo-simulation nuclear-engineering openmc

Last synced: 18 Jan 2026

https://github.com/inr-kit/McCAD-Library

a CAD to MC geometry conversion tool

boostcpp cmake cpluplus mcnp opencascade

Last synced: 04 Apr 2025

https://github.com/watts-dev/watts

Workflow and Template Toolkit for Simulation (WATTS)

mcnp nuclear-energy openmc python simulation templates workflow-automation

Last synced: 14 Jan 2026

https://github.com/idaholab/montepy

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

api mcnp mcnp6 monte-carlo neutronics radiation-transport

Last synced: 09 Apr 2025

https://github.com/fusion-energy/neutronics_material_maker

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

database fispact library material mcnp neutrons openmc serpent

Last synced: 19 Feb 2026

https://github.com/iaea-nds/acemaker

A code package to produce ACE-formatted files for MCNP calculations.

ace mcnp nuclear-data

Last synced: 18 Jan 2026

https://github.com/kordusas/npp_mcnp_plugin

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

ide mcnp notepad-plus-plus python27

Last synced: 09 Apr 2025

https://github.com/niess/gdnp

Convert a GDML geometry to an MCNP card

converter gdml mcnp

Last synced: 27 Mar 2025

https://github.com/dvp2015/tokamakneutronsource.jl

Methods to compute neutron source for a given plasma equilibrium state presented with EQDSK file

mcnp neutron openmc plasma

Last synced: 22 Feb 2026