Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Fusion Engineering (Tokamak/Stellarator)

Online master's programme of 1,900 hours in fusion engineering (tokamak/stellarator), structured in 12 modules covering toroidal magnetic confinement, MHD equilibrium, stability and disruptions, transport, stellarator optimisation, heating and current drive, power exhaust, diagnostics, plasma control and device engineering, with an assigned technical tutor.

Duration1900 h
ModeOnline
LanguageEnglish
Start datesSet by the faculty
AwardSEIUM Institute diploma

Master’s in Fusion Engineering (Tokamak/Stellarator) — studying from the United Kingdom

The United Kingdom has a long history in nuclear engineering and maintains a substantial sector spanning reactor operation, decommissioning, fuel cycle and new build projects. Sites at Sellafield, Hinkley Point, Dounreay and Harwell host work on fuel cycle, waste management and advanced reactor technology. Organisations such as the Nuclear Decommissioning Authority, EDF, Rolls-Royce SMR and Urenco UK employ engineers in design, safety and operations. Nuclear activities are overseen by the Office for Nuclear Regulation, which sets strict safety and security requirements.

Fees for the United Kingdom: £8,280 (Pound sterling), with instalments and employer sponsorship available.

Relevant bodies in the United Kingdom

  • Office for Nuclear Regulation (ONR)
  • Nuclear Decommissioning Authority (NDA)
  • Nuclear Institute
  • Institution of Mechanical Engineers (IMechE)

Typical roles

  • Nuclear Engineer
  • Fuel Cycle Engineer
  • Decommissioning Engineer
  • Nuclear Safety Engineer

Questions from the United Kingdom

Which UK regulators and bodies govern nuclear engineering, and how do they treat private training?

The Office for Nuclear Regulation regulates nuclear safety in the UK, and the Nuclear Institute is the main professional body. Competence requirements for licensed sites are set by the operator and regulator. SEIUM's qualifications are private, not state degrees, and not accredited by any national body, so they carry no regulatory standing and recognition is at the discretion of employers and the Nuclear Institute.

Do UK nuclear operators and fuel cycle employers hire people with private online qualifications?

UK nuclear employers typically require security clearance, specific competence assessments and qualifications recognised within the industry. A private online qualification may add to your profile but is unlikely to replace formal requirements. Employers decide its value, so check the entry criteria for roles you want before investing in the programme.

How intensive is the programme, and can I fund it through employer sponsorship in the UK?

Specialist courses take 300 hours, postgraduate diplomas 800 hours and master's programmes 1,900 hours, all online in English with an assigned technical tutor. Fees can be paid in instalments. Employer sponsorship is possible, and many UK nuclear employers run their own training schemes, so ask whether your employer would fund this specifically.

Virtual lab · try it before you enrol

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.

SIM · LIVE ●
Learning outcomes

What you will be able to do

01

Understand the topology of toroidal magnetic confinement.

02

Calculate MHD equilibria in tokamaks and stellarators.

03

Analyse plasma stability and disruptions.

04

Model transport and confinement.

05

Optimise stellarator configurations.

06

Design heating, diagnostic and control systems.

07

Assess future fusion reactor concepts.

Profile

Who it's for

  • Plasma physicists.
  • Fusion engineers.
  • Plasma control engineers.
  • Diagnostics specialists.
  • Plasma heating engineers.
  • Researchers in stellarator optimisation.
  • Engineering or science graduates seeking to enter the fusion energy sector.
Standards & tools

What you'll work with

  • ITER Physics Basis (reference physics basis for ITER design)
  • IAEA SSG-91 (safety of fusion facilities)
  • ASME BPVC Section III Division 4 (rules for fusion energy devices)
  • RCC-MRx (design and construction rules for mechanical components of nuclear installations)
  • IEC 61788 (superconductivity measurements)
  • ISO 21009 (cryogenic vessels)
  • IEC 61508 (functional safety of electrical/electronic/programmable systems)
  • FreeGS
  • VMEC
  • SIMSOPT
  • SOLPS-ITER
  • IMAS
Syllabus

12 modules · 1900 h

  1. 1.1Toroidal topology and rotational transform
  2. 1.2Magnetic surfaces
  3. 1.3Flux coordinates
  4. 1.4Safety factor q
  5. 1.5Tokamak: plasma current
  6. 1.6Stellarator: confinement by external coils
  7. 1.7Tokamak-stellarator comparison
  8. 1.8Reference devices: JET, ITER, W7-X and JT-60SA
  9. 1.9European programmes
  10. 1.10Case study: comparative analysis of W7-X and ITER
  1. 2.1Ideal MHD equations
  2. 2.2Force and pressure balance
  3. 2.3The Grad-Shafranov equation
  4. 2.4Shaped plasmas: elongation and triangularity
  5. 2.5Plasma beta
  6. 2.63D equilibrium in stellarators
  7. 2.7The VMEC code
  8. 2.8Equilibrium reconstruction with EFIT
  9. 2.9Plasma shape control
  10. 2.10Lab: solving Grad-Shafranov with FreeGS
  1. 3.1Ideal and resistive modes
  2. 3.2Kink and ballooning modes
  3. 3.3Tearing modes and NTMs
  4. 3.4Edge-localised modes (ELMs)
  5. 3.5Operational limits
  6. 3.6Disruptions and their physics
  7. 3.7Runaway electrons
  8. 3.8Disruption mitigation
  9. 3.9Prediction with machine learning
  10. 3.10Practical exercise: stability analysis with public data
  1. 4.1Neoclassical transport
  2. 4.2Turbulent transport
  3. 4.3ITG and TEM turbulence modes
  4. 4.4IPB98 confinement time scaling
  5. 4.5H-mode and the pedestal
  6. 4.6Neoclassical optimisation in stellarators
  7. 4.7Gyrokinetic simulation
  8. 4.8Integrated transport models
  9. 4.9The ASTRA and JINTRAC codes
  10. 4.10Lab: transport simulation with a 1D model
  1. 5.1Quasi-symmetry theory
  2. 5.2Quasi-isodynamicity and omnigeneity
  3. 5.3Numerical optimisation of configurations
  4. 5.4The STELLOPT and SIMSOPT codes
  5. 5.5Coil design
  6. 5.6Manufacturing tolerances
  7. 5.7Magnetic islands and the island divertor
  8. 5.8Lessons from Wendelstein 7-X
  9. 5.9Compact stellarators
  10. 5.10Practical exercise: coil optimisation with SIMSOPT
  1. 6.1Ohmic heating
  2. 6.2Neutral beam injection
  3. 6.3Electron cyclotron resonance heating (ECRH)
  4. 6.4Ion cyclotron resonance heating (ICRH)
  5. 6.5Lower hybrid waves
  6. 6.6Non-inductive current drive
  7. 6.7Gyrotrons
  8. 6.8Negative ion sources
  9. 6.9Coupling to the plasma
  10. 6.10Case study: heating power balance
  1. 7.1Plasma edge physics
  2. 7.2The scrape-off layer (SOL)
  3. 7.3Divertor configurations
  4. 7.4Plasma detachment
  5. 7.5Radiation and impurity seeding
  6. 7.6Loads on divertor targets
  7. 7.7The SOLPS-ITER codes
  8. 7.8Advanced divertors
  9. 7.9Island divertor in stellarators
  10. 7.10Lab: estimation of divertor loads
  1. 8.1Magnetics: coils and flux loops
  2. 8.2Interferometry and polarimetry
  3. 8.3Thomson scattering
  4. 8.4Spectroscopy
  5. 8.5Neutron diagnostics
  6. 8.6Bolometry
  7. 8.7Reflectometry
  8. 8.8Integration of diagnostics in ITER
  9. 8.9Integrated data analysis
  10. 8.10Practical exercise: analysis of Thomson scattering profiles
  1. 9.1Real-time control systems
  2. 9.2Vertical position control
  3. 9.3Shape control
  4. 9.4Profile control
  5. 9.5Density control
  6. 9.6Machine protection
  7. 9.7Reinforcement learning in control
  8. 9.8ITER control architectures
  9. 9.9Control simulators
  10. 9.10Lab: simplified vertical control in Simulink
  1. 10.1Vacuum vessel
  2. 10.2Superconducting coils
  3. 10.3Cryostat and cryogenics
  4. 10.4In-vessel components
  5. 10.5Remote maintenance
  6. 10.6Electrical power supply systems
  7. 10.7Integration and assembly
  8. 10.8Lessons from the ITER assembly
  9. 10.9Manufacturing of non-planar coils
  10. 10.10Workshop: analysis of assembly tolerances
  1. 11.1DEMO design
  2. 11.2Spherical reactors: STEP
  3. 11.3Compact high-field tokamaks
  4. 11.4Stellarator reactors
  5. 11.5Availability and maintenance
  6. 11.6The tritium cycle
  7. 11.7Materials and the IFMIF-DONES source
  8. 11.8Safety and licensing
  9. 11.9Fusion economics
  10. 11.10Case study: comparison of reactor concepts
  1. 12.1Definition of the confinement problem
  2. 12.2Literature review
  3. 12.3Selection of models and codes
  4. 12.4Equilibrium or transport calculation
  5. 12.5Stability or control analysis
  6. 12.6Engineering implications
  7. 12.7Discussion of results
  8. 12.8Conclusions
  9. 12.9Master's Thesis: written report
  10. 12.10Master's Thesis: defence before a panel
Methodology, software & labs

How you'll learn

100% online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. There are no fixed timetables: you progress at your own pace within each intake, so the programme can be combined with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is FreeGS, VMEC, SIMSOPT, SOLPS-ITER and IMAS, in free, academic or evaluation versions. Practical work is based on real procedures for MHD equilibrium calculation, stellarator configuration optimisation and analysis of plasma diagnostic data. Assessment is continuous by module, plus the final Master's Thesis.

Standards covered: ITER Physics Basis, IAEA SSG-91, ASME BPVC Section III Division 4, RCC-MRx, IEC 61788, ISO 21009, IEC 61508.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of the ITER Physics Basis, IAEA SSG-91 and ASME BPVC Section III Division 4 applied to real cases, not as a theoretical annex.
Industry software:FreeGS, VMEC, SIMSOPT, SOLPS-ITER and IMAS, in free, academic or evaluation versions.
Master's Thesis with defence:A confinement study for a tokamak or stellarator, from equilibrium or transport calculation to stability or control analysis and its engineering implications, defended before a panel.
Flexible format:100% online, no fixed timetables, compatible with full-time work.
Capstone project

Build it end to end

Your final project follows the real engineering workflow, step by step, reviewed by your tutor.

Define the confinement problem
Set out the device and the physics question to address, supported by a literature review.
Select models and codes
Choose the appropriate equilibrium, transport or stability tools, such as FreeGS, VMEC or SIMSOPT.
Calculate equilibrium or transport
Compute the MHD equilibrium or transport profiles for the chosen configuration.
Analyse stability or control
Evaluate stability limits or control performance and derive the engineering implications.
Master's Thesis
Discuss the results, draw conclusions and present the complete study, defended before a panel.
Career opportunities

Where this takes you

Plasma physicistFusion engineerPlasma control engineerDiagnostics specialistPlasma heating engineerStellarator optimisation researcher
Admissions & scholarships

Requirements

  • University degree in engineering, science or architecture, or equivalent demonstrable professional experience.
  • Internet connection and a computer capable of running the programme software.
  • English sufficient to read technical standards.

Ready to start?

Send your application today. Our admissions team replies within 72 hours with your study plan and funding options.

FAQ

Frequently asked questions

The programme totals 1,900 hours over 12–14 months. You set your own pace within each intake, and your tutor helps you plan the workload around your job.

You work with FreeGS, VMEC, SIMSOPT, SOLPS-ITER and IMAS, using free, academic or evaluation versions. Your tutor indicates the free alternative wherever one exists.

A SEIUM Institute diploma, awarded on passing the continuous assessment and the Master's Thesis. It is SEIUM's own qualification, not an official state degree; its recognition depends on the programme completed and the regulations of each country.

Yes. Modules passed in a course or postgraduate diploma in the same area are recognised in the higher programme. Ask about the recognition policy when you enrol.

A university degree in engineering, science or architecture (or equivalent professional experience), a computer able to run the programme software and English sufficient to read technical standards.

Start dates are set by SEIUM's faculty for each intake. Our admissions team will confirm the next available date when you apply.

Master’s in Fusion Engineering (Tokamak/Stellarator)Enrol
Scroll to Top
SEIUM – Institute of Advanced Engineering
Privacy Overview

This website uses cookies so that we can provide you with the best user experience possible. Cookie information is stored in your browser and performs functions such as recognising you when you return to our website and helping our team to understand which sections of the website you find most interesting and useful.