A method of characteristics code for nuclear reactor physics calculations.
☆193Jul 19, 2024Updated 2 years ago
Alternatives and similar repositories for OpenMOC
Users that are interested in OpenMOC are comparing it to the libraries listed below. We may earn a commission when you buy through links labeled 'Ad' on this page.
Sorting:
- OpenMC Monte Carlo Code☆1,114Updated this week
- Nuclear data processing with legacy NJOY☆136Jul 23, 2026Updated 2 months ago
- High-Fidelity Multiphysics☆153Updated this week
- PyNE: The Nuclear Engineering Toolkit☆319Sep 3, 2026Updated last month
- OpenMC wrapped as a Moose App☆16May 1, 2023Updated 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.
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆49Dec 24, 2025Updated 9 months ago
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆31May 19, 2021Updated 5 years ago
- An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool☆30Jan 9, 2021Updated 5 years ago
- A method of characteristics-based nuclear reactor physics simulator☆17Oct 5, 2022Updated 4 years ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆65Sep 2, 2026Updated last month
- Direct Accelerated Geometry Monte Carlo Toolkit☆133Sep 3, 2026Updated last month
- Open Nodal Core Simulator☆83Aug 24, 2026Updated last month
- Workflow and Template Toolkit for Simulation (WATTS)☆39Jul 24, 2026Updated 2 months ago
- Format description for ACE nuclear data files☆23Apr 28, 2022Updated 4 years ago
- 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 curated list of open source projects used in nuclear science and engineering☆507Feb 4, 2026Updated 8 months ago
- Stochastic Calculator Of Neutron transport Equation☆64Jul 28, 2026Updated 2 months ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆70Jul 21, 2023Updated 3 years ago
- Catalogs a plethora of reactor inputs for OpenMC☆42Feb 28, 2025Updated last year
- Collection of models for reactor physics benchmarks☆69Sep 17, 2025Updated last year
- Repository for Moltres, a code for simulating Molten Salt Reactors☆85Updated this week
- The Cyclus Nuclear Fuel Cycle Simulator☆94Oct 3, 2026Updated last week
- Native plotting GUI for model design and verification☆74Sep 3, 2026Updated last month
- Collection of scripts for managing data for OpenMC☆41Aug 1, 2026Updated 2 months ago
- 1-Click AI Models by DigitalOcean Gradient • AdDeploy popular AI models on DigitalOcean Gradient GPU virtual machines with just a single click. Zero configuration with optimized deployments.
- NJOY for the 21st Century☆92Jan 22, 2024Updated 2 years ago
- A C++ Monte Carlo Neutron Transport Code☆19Dec 10, 2025Updated 9 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Sep 13, 2021Updated 5 years ago
- A nuclear reactor lattice physics code.☆26Sep 23, 2026Updated 2 weeks ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆78Updated this week
- Tools to translate between different CSG geometry types☆44May 28, 2025Updated last year
- DRAGON V5 reactor physics code workshop with useful scripts and examples☆13Aug 4, 2025Updated last year
- Nuclear Reactor Theory☆21Nov 9, 2017Updated 8 years ago
- A 3D Method of Characteristics (MOC) reactor simulation Mini-App featuring MPI and OpenMP parallelism☆17Jan 4, 2023Updated 3 years ago
- 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.
- Contains slides and example problems for OpenMC workshops and presentations☆28Jun 13, 2022Updated 4 years ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆66Sep 29, 2026Updated last week
- Simulation of transmutation and decay in nuclear systems☆38Updated this week
- In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.☆21Sep 27, 2020Updated 6 years ago
- List of open source projects related to OpenMC☆42May 22, 2026Updated 4 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆101Sep 12, 2026Updated 3 weeks ago
- THOR is a radiation transport code for unstructured meshes.☆17Sep 17, 2024Updated 2 years ago