rachelslaybaugh / NE250
Nuclear Reactor Theory
☆19Updated 7 years ago
Related projects ⓘ
Alternatives and complementary repositories for NE250
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 4 months ago
- Stochastic Calculator Of Neutron transport Equation☆36Updated last month
- Collection of models for reactor physics benchmarks☆48Updated last month
- Sampling nuclear data and uncertainty☆48Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆63Updated last year
- Native plotting GUI for model design and verification☆47Updated 3 weeks ago
- open-source Sn software☆21Updated this week
- Repository for Moltres, a code for simulating Molten Salt Reactors☆65Updated last week
- Nuclear data processing with legacy NJOY☆98Updated 3 weeks ago
- Collection of scripts for managing data for OpenMC☆27Updated 11 months ago
- List of open source projects related to OpenMC☆21Updated 2 months ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆50Updated this week
- A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes☆57Updated 3 weeks ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 2 months ago
- A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant☆32Updated 3 years ago
- curated documents pertaining to early molten salt reactor research.☆21Updated 8 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆36Updated 4 months ago
- OpenMC wrapped as a Moose App☆16Updated last year
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆27Updated 6 years ago
- NJOY for the 21st Century☆73Updated 9 months ago
- continuous energy monte carlo neutron transport in general geometries on GPUs☆42Updated 7 years ago
- Contains slides and example problems for OpenMC workshops and presentations☆23Updated 2 years ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- ☆28Updated last year
- OpenMC Monte Carlo Code☆14Updated 2 months ago
- ☆17Updated 2 months ago
- Format description for ACE nuclear data files☆19Updated 2 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆104Updated last month
- Toolkit for reading and interacting with ENDF-6 formatted files☆34Updated 2 weeks ago