Course on Radiation Safety in Fusion Facilities
Online course of 300 h in Radiation Safety in Fusion Facilities. 6 modules covering Directive 2013/59/Euratom (basic safety standards), IAEA GSR Part 3 (radiation protection) and MCNP. Dedicated tutor and enrolment open.
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
Identify the sources of radiological risk in fusion facilities.
Explain the neutron activation of structural materials.
Analyse tritium management and confinement.
Apply the ICRP system of radiological protection.
Calculate doses with radiation transport tools.
Design the radiological zoning of a facility.
Assess the regulatory framework applicable to ITER and future fusion power plants.
Who it's for
- Radiation protection technician in fusion looking to specialise in Radiation Safety in Fusion Facilities.
- Nuclear safety engineer looking to specialise in Radiation Safety in Fusion Facilities.
- Neutronics engineer looking to specialise in Radiation Safety in Fusion Facilities.
- Tritium management specialist looking to specialise in Radiation Safety in Fusion Facilities.
- Activated waste technician looking to specialise in Radiation Safety in Fusion Facilities.
- Fusion safety researcher looking to specialise in Radiation Safety in Fusion Facilities.
- Engineering or science graduates looking to move into nuclear fusion.
What you'll work with
- Directive 2013/59/Euratom (basic safety standards)
- IAEA GSR Part 3 (radiation protection)
- ICRP Publication 103
- Spanish Royal Decree 1029/2022 (health protection against ionising radiation)
- ISO 2889 (sampling radioactive effluents from stacks)
- ISO 17873 (ventilation of nuclear facilities)
- French INB Order of 7 February 2012 (basic nuclear installations)
6 modules · 300 h
1.114 MeV neutrons1.2Prompt and delayed gamma radiation1.3Activation of structures and coolant1.4Activated corrosion products1.5Tritium as a radiological source1.6Activated and tritiated dust1.7X-rays from runaway electrons1.8Comparison with fission facilities1.9Dosimetric quantities and units1.10Practice: inventory of radiological sources in a tokamak
2.1Neutron transport in fusion2.2MCNP and OpenMC with CAD models2.3Activation calculation with FISPACT-II2.4Shutdown dose and the R2S method2.5Bioshield design2.6Penetrations and radiation streaming2.7JET benchmarks2.8FENDL data libraries2.9Uncertainties in activation2.10Lab: shutdown dose rate with R2S
3.1Justification, optimisation and limitation3.2Radiological zoning3.3ALARA programme in fusion3.4Personal and area dosimetry3.5Tritium contamination control3.6Ventilated suits and respiratory protection3.7Remote maintenance to reduce dose3.8Access control3.9Training of exposed workers3.10Case study: ALARA plan for an in-vessel intervention
4.1Safety functions in fusion4.2Confinement of tritium and dust4.3Loss of coolant in the vacuum vessel4.4Air or water ingress4.5Hydrogen and dust deflagration4.6Fire in tritium systems4.7ITER accident analysis4.8Releases and dose to the public4.9Defence in depth applied to fusion4.10Workshop: analysis of a loss-of-vacuum event
5.1Activated fusion waste5.2Clearance and recycling of materials5.3Directive 2013/59/Euratom5.4IAEA Basic Safety Standards GSR Part 35.5ITER's regulatory framework in France5.6National health protection regulations (e.g. Spain)5.7Environmental radiological monitoring5.8JET's decommissioning experience5.9Communication with the public5.10Case study: classification of first-wall waste
6.1Description of the facility6.2Identifying sources6.3Shielding and activation calculations6.4Zoning and ALARA plan6.5Accident analysis6.6Waste management6.7Assessment of dose to the public6.8Conclusions and recommendations6.9Report and presentation6.10Final review with the tutor
How you'll learn
100% online training on the SEIUM campus, with downloadable materials, recorded classes and a dedicated technical tutor. No fixed timetable: students progress at their own pace within the intake period, making it easy to combine with work.
Each module combines theory, guided reading of the original standards and applied exercises. The software used is MCNP, FISPACT-II, OpenMC, MicroShield, in free, academic or trial versions. Testing is studied through real procedures from activation calculation of components, tritium dose assessment, radiological zoning analysis. Assessment is continuous for each module, plus a final capstone project.
Build it end to end
Your final project follows the real engineering workflow, step by step, reviewed by your tutor.
Identify the sources of radiological risk in fusion facilities.
Explain the neutron activation of structural materials.
Analyse tritium management and confinement.
Apply the ICRP system of radiological protection.
Calculate doses with radiation transport tools.
Where this takes you
Requirements
- No previous qualification is required.
- An internet connection and a computer able to run the programme software.
- A level of 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.
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 MCNP, FISPACT-II, OpenMC, MicroShield. Free, academic or trial versions are used, and your tutor will point out a free alternative where one exists.
A SEIUM Institute diploma, awarded on passing the continuous assessment and the capstone project. It is SEIUM's own qualification, not an official state-accredited degree.
Yes. Modules passed in a course or postgraduate diploma in the same area are recognised in the higher programme. Check the credit recognition policy when you enrol.
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