MCNP

Some Monte Carlo tools

Tools to work with MCNP models and results

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

Python tools for MCNP

Materials that are dependent on conditions

a tool for creating axially symetric CSG geometry

Tool for converting MCNP input files to OpenMC classes/XML

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

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

Workflow and Template Toolkit for Simulation (WATTS)

MCNP SDEF to OpenMC conversion tool

Create an arbitrary parametric tokamak neutron source

GenNJOY is an open-source Python framework designed to automate the generation of high-fidelity, continuous-energy nuclear data libraries. It serves as a robust interface between raw Evaluated Nuclear Data Files (ENDF-6 format) and the NJOY2016 nuclear data processing system, streamlining the creation of ACE and HDF5 libraries for Monte Carlo codes

A Python library to assemble and apply transformations to MCNP files.

Full Monte Carlo shielding design of a real 15 MV medical linac vault using MCNP6.3 – neutron + gamma dose maps, maze attenuation, borated-PE door weight calculation. NCRP 151 compliant. Real Iranian hospital geometry (2025).

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

Monte Carlo tools for use with MCNP input or output for data processing.

Tool to convert MCNP geometries into TRIPOLI-4 geometries.

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

Tools used for MCNP input deck syntax highlighting