Stellarators Course and Its Academic Potential
Online 300-hour course on stellarators and its academic potential. 6 modules covering ASME BPVC Section III, Division 4 (fusion devices), RCC-MRx (mechanical design of high-temperature components) and VMEC. Dedicated tutor and open enrolment.
Take the controls.
Run a real engineering trade-off from this field. Move the sliders, watch the model react in real time and beat the challenge.
What you will be able to do
Explain toroidal magnetic confinement in stellarators.
Compare the stellarator concept with the tokamak.
Analyse magnetohydrodynamic equilibrium and stability.
Describe neoclassical transport and configuration optimisation.
Identify the engineering challenges of three-dimensional coils.
Assess the results of Wendelstein 7-X and TJ-II.
Develop a simplified conceptual stellarator design.
Who it's for
- Plasma physicist who wants to specialise in Stellarators and their academic potential.
- Stellarator design engineer who wants to specialise in Stellarators and their academic potential.
- Nuclear fusion researcher who wants to specialise in Stellarators and their academic potential.
- Magnetic coil engineer who wants to specialise in Stellarators and their academic potential.
- Fusion data analyst who wants to specialise in Stellarators and their academic potential.
- Fusion systems integration engineer who wants to specialise in Stellarators and their academic potential.
- Engineering or science graduates seeking to enter nuclear fusion.
What you'll work with
- ASME BPVC Section III, Division 4 (fusion devices)
- RCC-MRx (mechanical design of components for high temperature)
- EN 13445 (unfired pressure vessels)
- Directive 2013/59/Euratom (basic safety standards)
- ISO 9001 (quality management)
- IEC 61508 (functional safety)
6 modules · 300 h
1.1Principles of plasma confinement1.2Magnetic surfaces and rotational transform1.3Tokamak versus stellarator1.4History: Spitzer and the Princeton C-Model1.5Absence of plasma current and disruptions1.6Symmetries and quasi-symmetries1.7Boozer flux coordinates1.8Magnetic islands and stochasticity1.9Dimensionless parameters: beta and collisionality1.10Practical: tracing field lines in a torus
2.1Three-dimensional MHD equilibrium2.2The VMEC code2.3Pfirsch-Schlüter and bootstrap currents2.4Beta limits2.5Interchange and ballooning modes2.6Magnetic well2.7Island divertor2.8Equilibria with islands using SPEC2.9Sensitivity to field errors2.10Laboratory: stellarator equilibrium with VMEC
3.1Neoclassical transport and the 1/ν regime3.2Omnigeneity and quasi-isodynamicity3.3Confinement of alpha particles3.4Turbulence and gyrokinetic simulation3.5Numerical optimisation with STELLOPT3.6SIMSOPT and DESC tools3.7Objective functions and trade-offs3.8Quasi-axisymmetric and quasi-helical configurations3.9Accuracy of optimised solutions3.10Workshop: optimising a configuration with SIMSOPT
4.1Three-dimensional coil design4.2Superconducting coils and tolerances4.3Manufacturing and assembly of Wendelstein 7-X4.4Divertor and heat management4.5ECRH, NBI and ICRH heating4.6Plasma diagnostics4.7Remote maintenance and modularity4.8Breeding blankets in stellarators4.9Costs and construction complexity4.10Case study: lessons from the construction of W7-X
5.1Wendelstein 7-X: recent results5.2LHD in Japan5.3HSX and CIEMAT's TJ-II5.4Privately developed stellarators5.5HELIAS and ARIES-CS reactor concepts5.6EUROfusion roadmap5.7University research with small devices5.8Thesis and collaboration opportunities5.9Comparison with the tokamak route5.10Case study: analysis of an experimental W7-X campaign
6.1Definition of scientific objectives6.2Selection of the type of quasi-symmetry6.3Equilibrium calculation6.4Configuration optimisation6.5Simplified coil design6.6Transport and alpha particle assessment6.7Engineering feasibility analysis6.8Comparison with existing devices6.9Report and presentation6.10Final review with the tutor
How you'll learn
100 % online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. No fixed timetable: students progress at their own pace within the intake, which makes it possible to combine study with work.
Each module combines theory, guided reading of the original standard and applied exercises. The working software is VMEC, STELLOPT, Python (SciPy), CATIA, COMSOL Multiphysics, in free, academic or evaluation versions. Case studies are based on real procedures for magnetic equilibrium calculations, optimisation of coil configurations and analysis of experimental stellarator data. Assessment is continuous, module by module, plus a final integrating project.
Build it end to end
Your final project follows the real engineering workflow, step by step, reviewed by your tutor.
Explain toroidal magnetic confinement in stellarators.
Compare the stellarator concept with the tokamak.
Analyse magnetohydrodynamic equilibrium and stability.
Describe neoclassical transport and configuration optimisation.
Identify the engineering challenges of three-dimensional coils.
Where this takes you
Requirements
- No prior degree required.
- Internet connection and a computer capable of running the programme's software.
- Sufficient Spanish to follow technical standards documentation.
Ready to start?
Send your application today. Our admissions team replies within 72 hours with your study plan and funding options.
Frequently asked questions
The programme comprises 300 hours in total, spread over 3 to 5 months. That is an average of 10 to 15 hours per week, compatible with a full-time job.
The programme uses VMEC, STELLOPT, Python (SciPy), CATIA and COMSOL Multiphysics. Free, academic or evaluation versions are used, and the tutor will point out a free alternative where one exists.
A SEIUM Institute own diploma upon passing continuous assessment and the integrating project. This is in-house training, not an official qualification from the Ministry.
Yes. Modules passed in a course or Postgraduate Diploma in the same area can be credited towards the advanced programme. Check the credit transfer policy when you enrol.
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