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Tokamaks Course: Operation and Design

Online 300-hour course on tokamaks: operation and design. 6 modules covering ASME BPVC Section III, Division 4 (fusion devices), RCC-MRx (mechanical design of high-temperature components) and EFIT. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesOctober / March
LocationEurope (Madrid)
AwardSEIUM Institute diploma
Enrol now View syllabus Ask an advisor
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Learning outcomes

What you will be able to do

01

Explain the operating principle of a tokamak.

02

Describe the magnet, vacuum and heating systems.

03

Analyse operating scenarios and discharge control.

04

Evaluate disruptions and edge-localised modes.

05

Conceptually size the divertor and the first wall.

06

Assess the safety and licensing framework of ITER.

07

Compare the ITER design with DEMO concepts.

Profile

Who it's for

  • Tokamak operation engineer seeking to specialise in Tokamaks: operation and design.
  • Plasma physicist seeking to specialise in Tokamaks: operation and design.
  • Plasma control engineer seeking to specialise in Tokamaks: operation and design.
  • Plasma-facing components engineer seeking to specialise in Tokamaks: operation and design.
  • Nuclear fusion researcher seeking to specialise in Tokamaks: operation and design.
  • Heating systems engineer seeking to specialise in Tokamaks: operation and design.
  • Graduates in engineering or science seeking to enter nuclear fusion.
Standards & tools

What you'll work with

  • ASME BPVC Section III, Division 4 (Fusion Devices)
  • RCC-MRx (Mechanical Design of High-Temperature Components)
  • Arrêté INB of 7 February 2012 (Basic Nuclear Installations)
  • Directive 2014/68/EU (Pressure Equipment)
  • Directive 2013/59/Euratom (Basic Safety Standards)
  • IEC 61508 (Functional Safety)
  • ISO 17873 (Ventilation of Nuclear Installations)
Syllabus

6 modules · 300 h

  1. 1.1D-T fusion reactions and the Lawson criterion
  2. 1.2Triple product and Q gain
  3. 1.3Particle motion in magnetic fields
  4. 1.4Toroidal configuration and rotational transform
  5. 1.5MHD equilibrium and the Grad-Shafranov equation
  6. 1.6Safety factor q and magnetic shear
  7. 1.7Beta limit and the Greenwald density limit
  8. 1.8Anomalous transport and turbulence
  9. 1.9IPB98(y,2) confinement time scaling
  10. 1.10Practice: calculating the triple product in a tokamak
  1. 2.1Vacuum vessel and cryostat
  2. 2.2Toroidal, poloidal and central solenoid coils
  3. 2.3First wall and plasma-facing materials
  4. 2.4Divertor and exhaust heat management
  5. 2.5Tritium breeding blanket
  6. 2.6Pumping and fuelling systems
  7. 2.7Plasma diagnostics
  8. 2.8Auxiliary heating systems
  9. 2.9Shielding and component activation
  10. 2.10Case study: ITER architecture
  1. 3.1Dielectric breakdown and plasma initiation
  2. 3.2Current ramp-up and flat-top phase
  3. 3.3L-mode and H-mode
  4. 3.4ELM modes and their mitigation
  5. 3.5Plasma position and shape control
  6. 3.6Disruptions and their mitigation
  7. 3.7Runaway electrons
  8. 3.8Neutral beam and RF heating
  9. 3.9Non-inductive current drive
  10. 3.10Laboratory: equilibrium reconstruction with JET data
  1. 4.1Thermal loading on the divertor
  2. 4.2Detached divertor and impurity radiation
  3. 4.3Tungsten and beryllium as wall materials
  4. 4.4Erosion, redeposition and tritium retention
  5. 4.514 MeV neutron damage
  6. 4.6EUROFER low-activation steels
  7. 4.7IFMIF-DONES facility
  8. 4.8Water and helium cooling
  9. 4.9Remote maintenance of internal components
  10. 4.10Workshop: thermal balance of a divertor module
  1. 5.1System design tools: PROCESS
  2. 5.2Aspect ratio and spherical tokamaks
  3. 5.3Compact high-field tokamaks
  4. 5.4Tritium fuel cycle
  5. 5.5Plant balance and energy conversion
  6. 5.6Plant availability and reliability
  7. 5.7Fusion safety and licensing
  8. 5.8European DEMO, STEP and ARC
  9. 5.9Economics of fusion energy
  10. 5.10Case study: comparing DEMO and ARC
  1. 6.1Defining the device mission
  2. 6.2Selecting the main parameters
  3. 6.3Equilibrium and stability calculation
  4. 6.4Confinement estimation
  5. 6.5Sizing of coils and structure
  6. 6.6Conceptual divertor design
  7. 6.7Power balance and Q
  8. 6.8Proposed operating scenario
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

100 % online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. No fixed timetables: students progress at their own pace within the intake, which makes it possible to combine the course with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is EFIT, JINTRAC, TRANSP, MATLAB, ANSYS Mechanical, in free, academic or evaluation versions. Assessments are based on real procedures for magnetic equilibrium reconstruction, plasma discharge analysis and divertor heat load studies. Assessment is continuous by module, plus the final integrating project.

Accreditable laboratories(EN ISO/IEC 17025) with a rotor test rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-oriented thesis:safety case, test plan, compliance dossier and operational limits.
Industry mentoring:lecturers with track record in training, , eVTOL/UAM and flight test.
Flexible format(hybrid/online), international cohorts and support from SEIUM Career Services.
Ethics and safety:safety-by-design approach, OT cyber-security, DIH and compliance as core pillars.
Capstone project

Build it end to end

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

Defining the device mission

Explain the operating principle of a tokamak.

Selecting the main parameters

Describe the magnet, vacuum and heating systems.

Equilibrium and stability calculation

Analyse operating scenarios and discharge control.

Confinement estimation

Evaluate disruptions and edge-localised modes.

Sizing of coils and structure

Conceptually size the divertor and the first wall.

Career opportunities

Where this takes you

Tokamak operation engineerPlasma physicistPlasma control engineerPlasma-facing components engineerNuclear fusion researcherHeating systems engineer
Admissions & scholarships

Requirements

  • No prior degree is required.
  • Internet connection and a computer capable of running the programme's software.
  • A level of Spanish sufficient 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.

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FAQ

Frequently asked questions

The programme totals 300 hours, spread over 3 to 5 months. That is an average of 10 to 15 hours per week, compatible with a full-time job.

You will work with EFIT, JINTRAC, TRANSP, MATLAB, ANSYS Mechanical. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

An own diploma from SEIUM Institute upon passing the continuous assessment and the integrating project. It is in-house training, not an official qualification from the Ministry.

Yes. Modules passed in a course or postgraduate diploma in the same area are credited towards the advanced programme. Check the credit transfer policy when you enrol.

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