Fusion-Power-Plant-Framework / bluemira
Bluemira is an integrated inter-disciplinary design tool for future fusion reactors. It incorporates several modules, some of which rely on other codes, to carry out a range of typical conceptual fusion reactor design activities.
☆67Updated this week
Related projects ⓘ
Alternatives and complementary repositories for bluemira
- Parametric 3-D CAD modeling toolset for stellarator fusion devices☆26Updated this week
- A collection of files that can be used as inputs in the codes commonly used in the Plasma Physics community.☆37Updated last month
- This is the GitHub repository for STELLOPT, the state-of-the-art stellarator optimization code.☆67Updated this week
- Stellarator Equilibrium and Optimization Suite☆97Updated this week
- Heat flux Engineering Analysis Toolkit☆53Updated last week
- PROCESS is a systems code at UKAEA that calculates in a self-consistent manner the parameters of a fusion power plant with a specified pe…☆36Updated this week
- Create parametric 3D fusion reactor CAD and neutronics models☆64Updated this week
- Modern toolbox for impurity transport, neutrals and radiation modeling in magnetically-confined plasmas☆40Updated 2 weeks ago
- Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS☆92Updated this week
- Meshing library for nuclear workflows☆42Updated last month
- KiNetic Orbit-averaging SOlver for Stellarators☆10Updated 10 months ago
- Free boundary Grad-Shafranov solver☆91Updated last month
- Routines for tokamak analysis☆20Updated 6 years ago
- SFINCS: the Stellarator Fokker-Planck Iterative Neoclassical Conservative Solver☆22Updated 3 weeks ago
- An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.☆11Updated 2 months ago
- 2D fluid simulation of plasma and neutrals in magnetic fusion devices☆34Updated this week
- Simons Stellarator Optimizer Code☆97Updated this week
- The Open FUSION Toolkit (OFT) is a suite of modeling tools, and their underlying finite element framework, for problems in plasma and fus…☆31Updated this week
- Easily access hydrogen transport properties☆15Updated this week
- Creates a plasma source as an openmc.source object from input parameters that describe the plasma☆28Updated 3 months ago
- ASCOT5 is a high-performance orbit-following code for fusion plasma physics and engineering☆31Updated this week
- POPCONs (Plasma OPerating CONtours)☆22Updated last week
- Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.☆36Updated 4 months ago
- Learn how to simulate hydrogen transport with FESTIM☆17Updated 3 weeks ago
- ☆17Updated 2 months ago
- List of interesting fusion open source projects☆13Updated 4 months ago
- The Stepped-Pressure Equilibrium Code, an advanced MRxMHD equilibrium solver.☆24Updated last month
- Python tools for magnetic equilibria in tokamak plasmas☆31Updated last year
- A tool for making reproducible materials and standardizing use across several neutronics codes☆20Updated last month
- Symplectic Integration Methods for Particle Loss Estimation☆16Updated last week