MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
☆65Sep 12, 2026Updated last week
Alternatives and similar repositories for MontePy
Users that are interested in MontePy are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆101Updated this week
- Python tools for MCNP☆22Jun 12, 2026Updated 3 months ago
- API for parsing and post-processing many MC simulations related files☆19Updated this week
- Tool for converting MCNP input files to OpenMC classes/XML☆62Updated this week
- Workflow and Template Toolkit for Simulation (WATTS)☆39Jul 24, 2026Updated last month
- Virtual machines for every use case on DigitalOcean • AdGet dependable uptime with 99.99% SLA, simple security tools, and predictable monthly pricing with DigitalOcean's virtual machines, called Droplets.
- Repository for running SINBAD benchmarks with OpenMC and UQ☆12May 18, 2022Updated 4 years ago
- List of open source projects related to OpenMC☆42May 22, 2026Updated 3 months ago
- ☆95May 30, 2024Updated 2 years ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆12Oct 20, 2022Updated 3 years ago
- Python ENDF Parser☆46Sep 3, 2026Updated 2 weeks ago
- Python Interface and Utility Functions for MCNP6☆21Apr 7, 2017Updated 9 years ago
- Collection of validation scripts, notebooks, results☆11Dec 23, 2025Updated 8 months ago
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆18Dec 11, 2025Updated 9 months ago
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆26Jul 30, 2026Updated last month
- 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.
- Openmc-FEnicsx for muLtiphysics tutorIAl☆19May 27, 2025Updated last year
- A Python-based Monte Carlo radiation transport code☆61Updated this week
- Stochastic Calculator Of Neutron transport Equation☆64Jul 28, 2026Updated last month
- Tools to translate between different CSG geometry types☆44May 28, 2025Updated last year
- Meshing library for nuclear workflows☆82Jun 8, 2026Updated 3 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆48Dec 24, 2025Updated 8 months ago
- Native plotting GUI for model design and verification☆74Sep 3, 2026Updated 2 weeks ago
- Collection of scripts for managing data for OpenMC☆41Aug 1, 2026Updated last month
- Accelerated Discretized Geometry☆29Sep 8, 2026Updated last week
- Managed Database hosting by DigitalOcean • AdPostgreSQL, MySQL, MongoDB, Kafka, Valkey, and OpenSearch available. Automatically scale up storage and focus on building your apps.
- Monte Carlo Particle Lists☆38Jun 29, 2026Updated 2 months ago
- Automated V&V for fusion relevant CAD-based benchmarks☆25Apr 8, 2026Updated 5 months ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆132Sep 3, 2026Updated 2 weeks ago
- For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data☆36Aug 21, 2026Updated 3 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆47Jun 25, 2024Updated 2 years ago
- JADE, a novel nuclear data libraries V&V tool☆41Sep 9, 2026Updated last week
- Convert OpenMC Geometry Components to CAD☆21Nov 22, 2024Updated last year
- Computational inputs, reference outputs and experimental data for V&V systems☆18May 26, 2026Updated 3 months ago
- NJOY for the 21st Century☆91Jan 22, 2024Updated 2 years ago
- Managed Kubernetes at scale on DigitalOcean • AdDigitalOcean Kubernetes includes the control plane, bandwidth allowance, container registry, automatic updates, and more for free.
- a CAD to MC geometry conversion tool☆62Apr 4, 2024Updated 2 years ago
- a companion for writing MCNP input decks☆15Apr 2, 2021Updated 5 years ago
- A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.☆16May 6, 2025Updated last year
- Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files☆63Sep 9, 2026Updated last week
- OpenMC Monte Carlo Code☆28Jan 31, 2025Updated last year
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆200Sep 8, 2026Updated last week
- Open-source Sn software☆72Sep 11, 2026Updated last week