ezsolti / RFP

Related projects ⓘ

Alternatives and complementary repositories for RFP

• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆37Updated last month
• eepeterson / openmc_fusion_benchmarks
  ☆17Updated 3 months ago
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆13Updated 5 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆21Updated 2 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆37Updated 5 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆48Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆36Updated last month
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆52Updated 5 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆21Updated this week
• paulromano / endf-python
  Python ENDF Parser
  ☆26Updated 3 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆14Updated 3 months ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆21Updated 8 months ago
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 2 months ago
• RemDelaporteMathurin / h-transport-materials
  Easily access hydrogen transport properties
  ☆15Updated this week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆35Updated last year
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆32Updated 3 years ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆57Updated last month
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆63Updated last year
• jlanversin / ONIX
  ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…
  ☆38Updated last year
• fusion-energy / cad_to_h5m
  Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
  ☆12Updated last year
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated last year
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆10Updated 2 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆23Updated this week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆25Updated 8 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆32Updated this week
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆48Updated last month
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆20Updated last month