Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Nuclear Fuel Cycle Engineering (Front-/Back-End)

Online master's programme of 1,900 hours in nuclear fuel cycle engineering (front end and back end). 12 modules covering mining, conversion and enrichment, fuel fabrication, spent fuel storage and transport, reprocessing, back-end waste management and fuel cycle economics, with Directive 2011/70/Euratom, IAEA SSR-6 and ORIGEN (SCALE), with an assigned technical tutor.

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

Master’s in Nuclear Fuel Cycle Engineering (Front-/Back-End) — studying from Ireland

Ireland has no nuclear power generation, and its nuclear engagement is centred on radiation protection, research, medical applications and international policy. The Radiological Protection Institute of Ireland, now part of the Environmental Protection Agency, regulates radiation sources and monitors radiation exposure. Engineers and scientists in this area typically work in research, healthcare, environmental monitoring, decommissioning oversight and nuclear safeguards. Professional standards and expertise are coordinated through national and international bodies, with Ireland participating in European and international nuclear safety frameworks.

Fees for Ireland: €9,930 (Euro), with instalments and employer sponsorship available.

Relevant bodies in Ireland

  • Environmental Protection Agency (EPA)
  • Health and Safety Authority (HSA)
  • Department of the Environment, Climate and Communications
  • Institute of Physics Ireland

Typical roles

  • Radiation Protection Engineer
  • Nuclear Safety Analyst
  • Health Physics Specialist
  • Radiological Monitoring Engineer

Questions from Ireland

Is Ireland a country with a nuclear power industry, and how is nuclear engineering professionally recognised here?

Ireland has no operating nuclear power plants, so nuclear engineering careers here are mainly in regulation, research, decommissioning oversight and international projects. The Radiological Protection Institute of Ireland is the national regulator for radiation protection. SEIUM's qualifications are private and not accredited by this or any national body, so recognition depends on employers or the relevant body.

How might employers in Ireland view this training for nuclear-related roles?

Given Ireland's limited domestic nuclear industry, relevant roles are often with regulators, research institutions or multinational employers. Those employers decide how much weight to give a private online qualification and will usually look for specific radiation protection or regulatory credentials. There is no guarantee of any role or outcome.

What should I consider about workload and language before enrolling?

The programme is fully online and taught in English, so you can study from Ireland at your own pace. Study durations are 300, 800 or 1,900 hours depending on the course, so plan your time carefully. Fees can be paid in instalments, employer sponsorship is possible, and an assigned technical tutor supports your progress.

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Learning outcomes

What you will be able to do

01

Understand every stage of the nuclear fuel cycle.

02

Calculate mass balances and enrichment requirements.

03

Describe fuel fabrication processes and their quality control.

04

Design interim storage solutions for spent fuel.

05

Apply the regulations for the transport of radioactive material.

06

Compare open and closed fuel cycle strategies.

07

Assess the economics and sustainability of the fuel cycle.

Profile

Who it's for

  • Fuel cycle engineers.
  • Spent fuel management engineers.
  • Uranium market analysts.
  • Interim storage engineers.
  • Radioactive material transport specialists.
  • Consultants advising on fuel cycle policy.
  • Engineering or science graduates seeking to join a nuclear fuel manufacturer.
Standards & tools

What you'll work with

  • Directive 2011/70/Euratom (responsible management of spent fuel and radioactive waste)
  • IAEA SSR-6 (safe transport of radioactive material)
  • IAEA SSR-4 (safety of nuclear fuel cycle facilities)
  • IAEA GSG-1 (classification of radioactive waste)
  • Joint Convention (safety of spent fuel and radioactive waste management)
  • 10 CFR Part 72 (independent storage of spent fuel)
  • Royal Decree 102/2014 (Spanish regulation on spent fuel and radioactive waste management)
  • ORIGEN (SCALE)
  • SERPENT
  • DYMOND
  • CLASS
  • MATLAB
Syllabus

12 modules · 1900 h

  1. 1.1Stages of the open and closed cycle
  2. 1.2Fuel cycle mass balance
  3. 1.3Uranium and thorium resources
  4. 1.4Uranium and enrichment markets
  5. 1.5Fuel cycle sustainability indicators
  6. 1.6Environmental impact of each stage
  7. 1.7IAEA and NEA fuel cycle scenarios
  8. 1.8National fuel cycle policies
  9. 1.9The fuel cycle in advanced reactors
  10. 1.10Case study: mass balance of a nuclear fleet
  1. 2.1Geology of uranium deposits
  2. 2.2Open-pit and underground mining
  3. 2.3In-situ leaching
  4. 2.4Milling processes: yellowcake
  5. 2.5Management of tailings and mining waste
  6. 2.6Restoration of mining sites
  7. 2.7Radiation protection in mining
  8. 2.8ENUSA's experience at Saelices
  9. 2.9Mining and radiological regulations
  10. 2.10Practical exercise: environmental assessment of a closed mine
  1. 3.1Chemistry of conversion to UF6
  2. 3.2Properties and handling of UF6
  3. 3.3Principles of isotope separation
  4. 3.4Separative work units
  5. 3.5Optimisation of tails assay
  6. 3.6Enrichment market and suppliers
  7. 3.7HALEU for advanced reactors
  8. 3.8Chemical safety of UF6
  9. 3.9Safeguards at enrichment facilities
  10. 3.10Workshop: calculation of SWU and natural uranium required
  1. 4.1Reconversion to UO2
  2. 4.2Pellet pressing and sintering
  3. 4.3Fabrication of cladding and skeletons
  4. 4.4Fuel assembly manufacturing
  5. 4.5Factory quality control
  6. 4.6The Juzbado plant
  7. 4.7MOX fuel fabrication
  8. 4.8Criticality safety in fabrication plants
  9. 4.9Licensing of fabrication facilities
  10. 4.10Case study: pellet quality control plan
  1. 5.1In-core fuel management
  2. 5.2Discharge burnup and its optimisation
  3. 5.3Isotopic inventory of spent fuel
  4. 5.4Decay heat and activity
  5. 5.5ORIGEN and depletion codes
  6. 5.6Fuel failures and their management
  7. 5.7Management of damaged fuel
  8. 5.8Cycle extension strategies
  9. 5.9Data for the back end
  10. 5.10Practical exercise: isotopic inventory with ORIGEN
  1. 6.1Spent fuel pools
  2. 6.2Reracking and pool capacity
  3. 6.3Dry cask storage
  4. 6.4Individual interim storage facility (ATI)
  5. 6.5Centralised interim storage facility
  6. 6.6Thermal analysis of casks
  7. 6.7Criticality and burnup credit
  8. 6.8Cask shielding
  9. 6.9Ageing during extended storage
  10. 6.10Workshop: thermal analysis of a metal cask
  1. 7.1IAEA SSR-6 Regulations
  2. 7.2Type A, B and C packages
  3. 7.3Packages for fissile material
  4. 7.4Transport of UF6
  5. 7.5Transport of spent fuel
  6. 7.6ADR, RID and IMDG agreements
  7. 7.7Package design approvals
  8. 7.8Transport emergency plans
  9. 7.9Physical protection in transport
  10. 7.10Case study: documentation for a fuel shipment
  1. 8.1PUREX process chemistry
  2. 8.2Separation of uranium and plutonium
  3. 8.3Vitrification of high-level waste
  4. 8.4Recycling into MOX and RepU
  5. 8.5Experience at La Hague and Sellafield
  6. 8.6Partitioning and transmutation
  7. 8.7Pyrometallurgical separation processes
  8. 8.8Fast reactors and multi-recycling
  9. 8.9Safeguards in reprocessing
  10. 8.10Practical exercise: comparison of open and closed cycles
  1. 9.1Waste classification according to GSG-1
  2. 9.2High-level waste
  3. 9.3Spent fuel as waste
  4. 9.4Deep geological disposal
  5. 9.5Experience at Onkalo and Forsmark
  6. 9.6Spain's General Radioactive Waste Plan
  7. 9.7Back-end financing
  8. 9.8Social acceptance and public participation
  9. 9.9Retrievability of disposed waste
  10. 9.10Case study: analysis of the 7th General Radioactive Waste Plan (PGRR)
  1. 10.1Levelised fuel cost
  2. 10.2Front-end costs
  3. 10.3Back-end costs
  4. 10.4Uranium supply contracts
  5. 10.5Strategic inventory management
  6. 10.6Geopolitical supply risk
  7. 10.7Economic sensitivity analysis
  8. 10.8Waste funds
  9. 10.9International cost comparison
  10. 10.10Workshop: fuel cycle cost for different strategies
  1. 11.1Criticality safety
  2. 11.2Radiation protection across the fuel cycle
  3. 11.3Nuclear material accountancy
  4. 11.4Proliferation resistance as a design criterion
  5. 11.5Ethics of the fuel cycle
  6. 11.6Carbon footprint of the fuel cycle
  7. 11.7Circular economy in the fuel cycle
  8. 11.8Dynamic scenarios with DYMOND and CLASS
  9. 11.9INPRO sustainability indicators
  10. 11.10Practical exercise: dynamic fleet transition scenario
  1. 12.1Definition of the fuel cycle strategy to be studied
  2. 12.2Collection of fleet data
  3. 12.3Mass balance model
  4. 12.4Technical assessment of alternatives
  5. 12.5Economic assessment of alternatives
  6. 12.6Impact and sustainability assessment
  7. 12.7Strategy recommendations
  8. 12.8Conclusions and recommended strategy
  9. 12.9Master's Thesis 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, making it compatible with full-time work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is ORIGEN (SCALE), SERPENT, DYMOND, CLASS and MATLAB, in free, academic or evaluation versions. Tests are studied using real procedures for fuel cycle scenario modelling, spent fuel storage analysis and economic assessment of back-end strategies. Assessment is continuous for each module, plus the final Master's Thesis.

Standards covered: Directive 2011/70/Euratom, IAEA SSR-6 Regulations for the Safe Transport of Radioactive Material, IAEA SSR-4 Safety of Nuclear Fuel Cycle Facilities, IAEA GSG-1 Classification of Radioactive Waste, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, 10 CFR Part 72 and Royal Decree 102/2014 on the management of spent fuel and radioactive waste.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of Directive 2011/70/Euratom, IAEA SSR-6 and IAEA SSR-4 applied to real cases, not as a theoretical annex.
Industry software:ORIGEN (SCALE), SERPENT, DYMOND, CLASS and MATLAB, in free, academic or evaluation versions.
Master's Thesis with defence:a fuel cycle strategy study with mass balance model and technical, economic and sustainability assessment of alternatives, 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.

Enrichment requirements calculation
You calculate the SWU and natural uranium needed to supply a reload.
Spent fuel isotopic inventory
You obtain the isotopic inventory and decay heat of spent fuel with ORIGEN.
Cask thermal analysis
You carry out the thermal analysis of a metal dry storage cask.
Dynamic fleet scenario
You model a fleet transition scenario and compare fuel cycle costs for different strategies.
Master's Thesis
A fuel cycle strategy study with mass balance and technical, economic and sustainability assessment of alternatives, defended before a panel.
Career opportunities

Where this takes you

Fuel cycle engineerSpent fuel management engineerUranium market analystInterim storage engineerRadioactive transport specialistFuel cycle policy consultant
Admissions & scholarships

Requirements

  • A university degree in engineering, science or architecture, or equivalent demonstrable professional experience.
  • An 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 ORIGEN (SCALE), SERPENT, DYMOND, CLASS and MATLAB, 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 Nuclear Fuel Cycle Engineering (Front-/Back-End)Enrol
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