NCSU-NCSG / THOR
THOR is a radiation transport code for unstructured meshes.
☆11Updated 4 months ago
Alternatives and similar repositories for THOR:
Users that are interested in THOR are comparing it to the libraries listed below
- Framework for REsearch in Nuclear ScIence and Engineering☆14Updated 3 years ago
- Stochastic Calculator Of Neutron transport Equation☆38Updated 3 weeks ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆39Updated 6 months ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- ENRICO: Exascale Nuclear Reactor Investigative COde☆64Updated last year
- A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.☆25Updated 3 years ago
- Collection of validation scripts, notebooks, results☆11Updated last year
- Collection of scripts for managing data for OpenMC☆29Updated last year
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 4 months ago
- continuous energy monte carlo neutron transport in general geometries on GPUs☆43Updated 7 years ago
- Helios - A C++ Monte Carlo Neutron Transport Code☆19Updated 4 years ago
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆51Updated this week
- open-source Sn software☆25Updated this week
- ☆18Updated 5 months ago
- Tools to translate between different CSG geometry types☆36Updated last year
- Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.☆20Updated 3 months ago
- Tool for converting MCNP input files to OpenMC classes/XML☆37Updated 3 weeks ago
- Native plotting GUI for model design and verification☆54Updated last month
- List of open source projects related to OpenMC☆22Updated 4 months ago
- Monte Carlo Particle Lists☆30Updated 10 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆53Updated 7 months ago
- Machine learning and artificial intelligence benchmarking library for nuclear engineering applications.☆22Updated 2 months ago
- Format description for ACE nuclear data files☆19Updated 2 years ago
- This repository holds codes from the book Computational Nuclear Engineering and Radiological Science with Python☆15Updated 4 years ago
- Collection of models for reactor physics benchmarks☆50Updated 3 months ago
- OpenMC wrapped as a Moose App☆16Updated last year
- Sampling nuclear data and uncertainty☆49Updated last week
- Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections☆10Updated 2 years ago
- OpenMC Monte Carlo Code☆17Updated 4 months ago
- ☆71Updated 7 months ago