arfc / moltres
Repository for Moltres, a code for simulating Molten Salt Reactors
☆67Updated 2 weeks ago
Alternatives and similar repositories for moltres:
Users that are interested in moltres are comparing it to the libraries listed below
- ENRICO: Exascale Nuclear Reactor Investigative COde☆64Updated last year
- High-Fidelity Multiphysics☆99Updated this week
- The Cyclus Nuclear Fuel Cycle Simulator☆81Updated last month
- Computational library for chemical thermodynamics and phase equilibrium calculation. Multiphysics and standalone estimations of chemical …☆48Updated 6 months ago
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆39Updated 6 months ago
- A suite of parsers designed to make interacting with SERPENT output files simple and flawless☆53Updated 6 months ago
- Stochastic Calculator Of Neutron transport Equation☆38Updated 3 weeks ago
- curated documents pertaining to early molten salt reactor research.☆21Updated 10 months ago
- Ducted Assembly Steady State Heat Transfer Software (DASSH)☆17Updated last year
- Simulation of transmutation and decay in nuclear systems☆27Updated this week
- continuous energy monte carlo neutron transport in general geometries on GPUs☆43Updated 7 years ago
- Direct Accelerated Geometry Monte Carlo Toolkit☆105Updated last week
- Workflow and Template Toolkit for Simulation (WATTS)☆25Updated 4 months ago
- ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…☆39Updated last month
- A tool for making reproducible materials and standardizing use across several neutronics codes☆22Updated 3 months ago
- Native plotting GUI for model design and verification☆54Updated last month
- The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository☆51Updated this week
- Online reprocessing for molten salt reactors☆20Updated this week
- code to target the conversion from a step-file to a h5m-geometry for neutronics☆32Updated last month
- detailed cad model of the msre☆34Updated 8 months ago
- ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…☆29Updated 7 months ago
- Sampling nuclear data and uncertainty☆49Updated last week
- A set of radiation transport mini-applications used for performance optimization on HPC systems.☆28Updated 6 years ago
- Collection of models for reactor physics benchmarks☆50Updated 3 months ago
- MC/DC: Monte Carlo Dynamic Code☆28Updated this week
- ☆18Updated last week
- Nuclear data processing with legacy NJOY☆99Updated 2 months ago
- Collection of scripts for managing data for OpenMC☆29Updated last year
- 2D fluid simulation of plasma and neutrals in magnetic fusion devices☆36Updated this week
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆27Updated this week