☆95May 30, 2024Updated 2 years ago
Alternatives and similar repositories for mcnptools
Users that are interested in mcnptools are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆65Updated this week
- Python tools for MCNP☆20Jun 12, 2026Updated last month
- Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis☆15Mar 19, 2021Updated 5 years ago
- Monte Carlo Particle Lists☆37Jun 29, 2026Updated 3 weeks ago
- Tool to rename cells, surfaces, materials and universes in MCNP input files.☆12Nov 25, 2022Updated 3 years ago
- Managed hosting for WordPress and PHP on Cloudways • AdManaged hosting for WordPress, Magento, Laravel, or PHP apps, on multiple cloud providers. Deploy in minutes on Cloudways by DigitalOcean.
- The package for producing gamma spec from nuclide activities☆13Jan 16, 2025Updated last year
- Gxsview: Geometry and cross section viewer for calculating radiation transport☆14Feb 11, 2021Updated 5 years ago
- Convert MCNP input files to a general CAD format☆40Jun 20, 2025Updated last year
- Python Interface and Utility Functions for MCNP6☆21Apr 7, 2017Updated 9 years ago
- Tool for converting MCNP input files to OpenMC classes/XML☆62May 1, 2026Updated 2 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆100Jun 25, 2026Updated 3 weeks ago
- Some Monte Carlo tools☆54Jun 30, 2026Updated 3 weeks ago
- NJOY for the 21st Century☆90Jan 22, 2024Updated 2 years ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Oct 20, 2022Updated 3 years ago
- Simple, predictable pricing with DigitalOcean hosting • AdAlways know what you'll pay with monthly caps and flat pricing. Enterprise-grade infrastructure trusted by 600k+ customers.
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆26Jun 25, 2026Updated 3 weeks ago
- A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact☆33Updated this week
- a CAD to MC geometry conversion tool☆61Apr 4, 2024Updated 2 years ago
- Convert OpenMC Geometry Components to CAD☆21Nov 22, 2024Updated last year
- A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak☆21Sep 13, 2021Updated 4 years ago
- A tool for making reproducible materials and standardizing use across several neutronics codes☆29Jul 10, 2026Updated last week
- API for parsing and post-processing many MC simulations related files☆19Updated this week
- ENDF/B pre-processing codes (PREPRO)☆23Aug 14, 2023Updated 2 years ago
- Tools to translate between different CSG geometry types☆44May 28, 2025Updated last year
- Deploy on Railway without the complexity - Free Credits Offer • AdConnect your repo and Railway handles the rest with instant previews. Quickly provision container image services, databases, and storage volumes.
- A utility code for generating material cards for MCNP☆24Feb 26, 2021Updated 5 years ago
- Nuclear data processing with legacy NJOY☆133Jun 1, 2026Updated last month
- A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)☆13Oct 24, 2012Updated 13 years ago
- OpenMC Monte Carlo Code☆28Jan 31, 2025Updated last year
- PyNE: The Nuclear Engineering Toolkit☆319Oct 22, 2025Updated 9 months ago
- Stochastic Calculator Of Neutron transport Equation☆62Jul 13, 2026Updated last week
- Python ENDF Parser☆42Jun 6, 2026Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆128Updated this week
- Thermal Scattering Library created with NJOY+NCrystal☆10May 4, 2022Updated 4 years ago
- GPUs on demand by Runpod - Special Offer Available • AdRun AI, ML, and HPC workloads on powerful cloud GPUs—without limits or wasted spend. Deploy GPUs in under a minute and pay by the second.
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆41Jul 3, 2025Updated last year
- NCrystal : a library for thermal neutron transport in crystals and other materials☆49Updated this week
- Toolkit for reading and interacting with ENDF-6 formatted files☆42Jun 24, 2026Updated 3 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆68Jul 21, 2023Updated 3 years ago
- Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files☆58Updated this week
- a companion for writing MCNP input decks☆14Apr 2, 2021Updated 5 years ago
- OpenMC Monte Carlo Code☆1,061Updated this week