openmsr / msreLinks
detailed cad model of the msre
☆39Updated 2 weeks ago
Alternatives and similar repositories for msre
Users that are interested in msre are comparing it to the libraries listed below
Sorting:
- Native plotting GUI for model design and verification☆64Updated 3 weeks ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆61Updated last month
- A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB☆17Updated 3 weeks ago
- Python ENDF Parser☆39Updated 3 weeks ago
- Tools to translate between different CSG geometry types☆40Updated 5 months ago
- MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.☆48Updated this week
- Direct Accelerated Geometry Monte Carlo Toolkit☆118Updated 9 months ago
- A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…☆167Updated this week
- Stochastic Calculator Of Neutron transport Equation☆51Updated 2 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆33Updated 4 months ago
- List of open source projects related to OpenMC☆29Updated 5 months ago
- High-Fidelity Multiphysics☆120Updated last week
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆24Updated 5 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆41Updated 4 years ago
- Sampling nuclear data and uncertainty☆52Updated last month
- NJOY for the 21st Century☆83Updated last year
- ☆32Updated 3 months ago
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆80Updated 2 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆43Updated last year
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆21Updated 4 months ago
- A method of characteristics code for nuclear reactor physics calculations.☆171Updated last year
- Automated V&V for fusion relevant CAD-based benchmarks☆23Updated 4 months ago
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆11Updated 3 years ago
- Format description for ACE nuclear data files☆22Updated 3 years ago
- Accelerated Discretized Geometry☆18Updated last week
- Tool for converting MCNP input files to OpenMC classes/XML☆49Updated 3 weeks ago
- ENRICO: Exascale Nuclear Reactor Investigative COde☆65Updated 2 years ago
- Collection of scripts for managing data for OpenMC☆37Updated this week
- Catalogs a plethora of reactor inputs for OpenMC☆34Updated 8 months ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆76Updated 2 weeks ago