imronuke / ADPRES
An Open Nuclear Reactor Simulator and Reactor Core Analysis Tool
☆23Updated 3 years ago
Related projects: ⓘ
- Open Nuclear Reactor Simulator☆46Updated 3 months ago
- THOR is a radiation transport code for unstructured meshes.☆11Updated this week
- Collection of scripts for managing data for OpenMC☆27Updated 9 months ago
- Stochastic Calculator Of Neutron transport Equation☆34Updated last week
- Framework for REsearch in Nuclear ScIence and Engineering☆13Updated 3 years ago
- Sampling nuclear data and uncertainty☆47Updated 2 weeks ago
- Native plotting GUI for model design and verification☆45Updated last month
- ENRICO: Exascale Nuclear Reactor Investigative COde☆61Updated last year
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆24Updated 3 years ago
- Repository for Moltres, a code for simulating Molten Salt Reactors☆66Updated this week
- MC/DC: Monte Carlo Dynamic Code☆20Updated this week
- OpenMC wrapped as a Moose App☆17Updated last year
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆52Updated 3 months ago
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 3 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆35Updated 2 months ago
- XSPlot - Neutron cross section plotter for isotopes☆14Updated last year
- Collection of models for reactor physics benchmarks☆48Updated 2 months ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- Monte Carlo Particle Lists☆28Updated 6 months ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆50Updated this week
- Nuclear data processing with legacy NJOY☆96Updated last month
- open-source Sn software☆18Updated this week
- Tools to translate between different CSG geometry types☆32Updated last year
- Collection of validation scripts, notebooks, results☆10Updated 11 months ago
- continuous energy monte carlo neutron transport in general geometries on GPUs☆42Updated 7 years ago
- ☆27Updated last year
- Online reprocessing for molten salt reactors☆19Updated 2 months ago
- Helios - A C++ Monte Carlo Neutron Transport Code☆18Updated 4 years ago
- A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy☆39Updated 3 years ago
- High-Fidelity Multiphysics☆89Updated last week