CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Breeding Blankets and Tritium Production Course

Online 300-hour course in breeding blankets and tritium production. 6 modules covering Décret n° 2012-1248 (authorisation for the creation of ITER, INB 174), Arrêté INB du 7 février 2012 (general rules for INBs) and OpenMC. Assigned tutor and enrolment open.

Duration300 h
ModeOnline
Start datesSet by the faculty
AwardSEIUM Institute certificate
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

Describe the tritium fuel cycle in a fusion reactor.

02

Compare the main breeding blanket concepts (HCPB, WCLL, DCLL).

03

Calculate the tritium breeding ratio through neutronic simulation.

04

Analyse the thermohydraulic and materials behaviour of the blanket.

05

Explain the tritium extraction and processing procedures.

06

Evaluate the safety and radiation protection aspects associated with tritium.

07

Develop a justified conceptual blanket design.

Profile

Who it's for

  • Fusion blanket design engineer wishing to specialise in Breeding Blankets and Tritium Production.
  • Fusion neutronics specialist wishing to specialise in Breeding Blankets and Tritium Production.
  • Tritium fuel cycle engineer wishing to specialise in Breeding Blankets and Tritium Production.
  • Fusion thermohydraulics engineer wishing to specialise in Breeding Blankets and Tritium Production.
  • Fusion materials researcher wishing to specialise in Breeding Blankets and Tritium Production.
  • Safety engineer for fusion facilities wishing to specialise in Breeding Blankets and Tritium Production.
  • Graduates in engineering or science seeking to join international fusion projects.
Standards & tools

What you'll work with

  • Décret No. 2012-1248 (INB 174)
  • Arrêté INB du 7 Février 2012 (General Rules for INBs)
  • Directive 2013/59/Euratom (Basic Safety Standards)
  • DOE-HDBK-1129 (Safe Handling and Storage of Tritium)
  • ASME BPVC Section III (Nuclear Components)
  • RCC-MRx (Design Rules for Advanced and Fusion Reactors)
Syllabus

6 modules · 300 h

  1. 1.1Properties of tritium
  2. 1.2Tritium scarcity and current sources
  3. 1.3Production reactions with lithium-6 and lithium-7
  4. 1.4Tritium breeding ratio (TBR)
  5. 1.5Neutron multipliers: beryllium and lead
  6. 1.6Tritium inventory in a plant
  7. 1.7Doubling time
  8. 1.8Losses and retention in materials
  9. 1.9Self-sufficiency requirements
  10. 1.10Workshop: tritium balance of a DEMO plant
  1. 2.1Blanket functions
  2. 2.2Helium-cooled solid breeder blanket (HCPB)
  3. 2.3Water-cooled lithium-lead blanket (WCLL)
  4. 2.4Helium-cooled lithium-lead blanket (HCLL)
  5. 2.5Dual-coolant blanket (DCLL)
  6. 2.6FLiBe molten salts
  7. 2.7Liquid lithium
  8. 2.8Performance comparison
  9. 2.9ITER TBM programme
  10. 2.10Case study: HCPB versus WCLL comparison
  1. 3.1Transport of 14 MeV neutrons
  2. 3.2FENDL nuclear data libraries
  3. 3.3TBR calculation with MCNP and OpenMC
  4. 3.4Lithium-6 enrichment
  5. 3.5Nuclear heat deposition
  6. 3.6Displacement damage (dpa)
  7. 3.7Helium production and transmutation
  8. 3.8Shielding of the superconducting magnet
  9. 3.9Activation and waste
  10. 3.10Laboratory: neutronic model of a blanket in OpenMC
  1. 4.1Heat extraction and temperature limits
  2. 4.2High-pressure helium cooling
  3. 4.3MHD effects in liquid metals
  4. 4.4Reduced-activation steel EUROFER97
  5. 4.5Compatibility and corrosion with lithium-lead
  6. 4.6Breeder ceramics and pebble beds
  7. 4.7Tritium permeation and barriers
  8. 4.8Thermal cycling and fatigue
  9. 4.9Manufacturing and joining
  10. 4.10Practice: thermal calculation of a cooling channel
  1. 5.1Tritium extraction from helium purge
  2. 5.2Extraction from lithium-lead
  3. 5.3Hydrogen isotope separation
  4. 5.4Detritiation of water and air
  5. 5.5Tritium confinement and safety
  6. 5.6Material accountancy
  7. 5.7Licensing of tritium facilities
  8. 5.8Test facilities: IFMIF-DONES
  9. 5.9Integration into a power plant
  10. 5.10Case study: extraction system for the European TBM
  1. 6.1Plant requirements
  2. 6.2Concept selection
  3. 6.3Neutronic model and TBR
  4. 6.4Thermohydraulic design
  5. 6.5Material selection
  6. 6.6Tritium extraction system
  7. 6.7Safety assessment
  8. 6.8Comparison with alternatives
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

Fully 100% online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. There are no fixed timetables: students progress at their own pace within the enrolment window, 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 OpenMC, MCNP, FISPACT-II, ANSYS Mechanical, COMSOL Multiphysics, in free, academic or evaluation versions. Tests are studied using real procedures for blanket mock-ups in lithium-lead loops, neutron irradiation of materials and neutronic simulation of the tritium breeding ratio. Assessment is continuous, module by module, plus the final integrative project.

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

Build it end to end

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

Plant requirements

Describe the tritium fuel cycle in a fusion reactor.

Concept selection

Compare the main breeding blanket concepts (HCPB, WCLL, DCLL).

Neutronic model and TBR

Calculate the tritium breeding ratio through neutronic simulation.

Thermohydraulic design

Analyse the thermohydraulic and materials behaviour of the blanket.

Material selection

Explain the tritium extraction and processing procedures.

Career opportunities

Where this takes you

Fusion blanket design engineerFusion neutronics specialistTritium fuel cycle engineerFusion thermohydraulics engineerFusion materials researcherSafety engineer for fusion facilities
Admissions & scholarships

Requirements

  • No prior degree is required.
  • Internet connection and a computer capable of running the programme's software.
  • Sufficient Spanish to follow technical regulatory texts.

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 consists of 300 hours in total, spread over 3 to 5 months. That is between 10 and 15 hours per week on average, compatible with a full-time job.

You will work with OpenMC, MCNP, FISPACT-II, ANSYS Mechanical, COMSOL Multiphysics. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

An own diploma from SEIUM upon passing the continuous assessment and the integrative 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.

Breeding Blankets and Tritium Production CourseEnrol
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.