Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Fission Reactor, Safety & Operation Engineering

Online master's programme of 1,900 hours in fission reactor engineering, safety and operation, structured in 12 modules covering fission and core physics, reactor kinetics and control, primary and secondary systems, defence in depth, safety systems, accident analysis, plant operation, maintenance and outages, radiation protection and nuclear regulation, with an assigned technical tutor.

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

Master’s in Fission Reactor, Safety & Operation Engineering — studying from South Africa

South Africa is one of the few African countries with an operating nuclear power programme, centred on the Koeberg power station near Cape Town, operated by Eskom. The country also has nuclear research and fuel cycle activity through the South African Nuclear Energy Corporation, known as Necsa, based at Pelindaba near Pretoria. Nuclear engineers work on reactor operation, safety, fuel management and decommissioning. The National Nuclear Regulator is the independent authority that licenses and oversees nuclear activities.

Fees for South Africa: R 185 000 (South African rand), with instalments and employer sponsorship available.

Relevant bodies in South Africa

  • National Nuclear Regulator (NNR)
  • South African Nuclear Energy Corporation (Necsa)
  • Eskom Holdings SOC Ltd

Typical roles

  • Nuclear Engineer
  • Reactor Safety Engineer
  • Nuclear Fuel Cycle Engineer
  • Radiation Protection Engineer

Questions from South Africa

Will a SEIUM qualification be recognised by the professional bodies in South Africa for this area?

SEIUM qualifications are private and not accredited by any South African body, so they are not official state degrees. Nuclear activities in South Africa are regulated by the National Nuclear Regulator (NNR), and professional registration runs through ECSA. Acceptance of a private qualification in this regulated field rests with employers or the relevant authority, so verify before enrolling.

How might this qualification be used by employers in South Africa in nuclear engineering?

Nuclear employers, including Eskom and specialist contractors, typically require formally recognised qualifications, security clearances and regulatory competence. A private SEIUM qualification may add background knowledge but is unlikely to meet formal requirements on its own. Discuss this with employers in the nuclear sector to understand how they would view it.

Can I study this programme alongside full-time work from South Africa, and is there a time zone or language issue?

The programme is fully online and taught in English, so you can study from South Africa without a student visa. Master's programmes require 1,900 hours, postgraduate diplomas 800 hours and specialist courses 300 hours, with an assigned technical tutor. Fees can be paid in instalments and employer sponsorship is possible. Ask SEIUM about time-zone and workload details before enrolling.

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Learning outcomes

What you will be able to do

01

Understand fission physics and nuclear reactor kinetics.

02

Distinguish the main reactor technologies and their safety features.

03

Apply the defence-in-depth principle to design and operation.

04

Analyse transients and accidents with recognised system codes.

05

Manage normal, abnormal and emergency operating procedures.

06

Plan maintenance and refuelling outages using ALARA criteria.

07

Interpret the national and international nuclear safety regulatory framework.

Profile

Who it's for

  • Nuclear operations engineers looking to deepen their knowledge of reactor safety and operation.
  • Nuclear safety engineers working on design or safety analysis.
  • Control room supervisors aiming to strengthen their technical grounding.
  • Accident analysis engineers working with system codes.
  • Licensing technicians dealing with regulators and safety documentation.
  • Nuclear maintenance engineers involved in outages and surveillance.
  • Engineering or science graduates seeking to enter the nuclear power sector.
Standards & tools

What you'll work with

  • Directive 2014/87/Euratom (EU nuclear safety framework for nuclear installations)
  • IAEA SSR-2/1 Safety of Nuclear Power Plants: Design (IAEA design safety requirements)
  • IAEA SSR-2/2 Safety of Nuclear Power Plants: Commissioning and Operation (IAEA requirements for commissioning and operation)
  • IAEA SF-1 Fundamental Safety Principles (IAEA fundamental safety principles)
  • Real Decreto 1217/2024 (Spanish regulation on nuclear and radioactive facilities)
  • 10 CFR Part 50 (US licensing of production and utilisation facilities)
  • ASME BPVC Section XI (in-service inspection of nuclear power plant components)
  • CSN Instruction IS-26 (Spanish basic nuclear safety requirements for nuclear installations)
  • RELAP5
  • TRACE
  • MELCOR
  • SERPENT
  • MATLAB
Syllabus

12 modules · 1900 h

  1. 1.1Nuclear structure, binding energy and mass defect
  2. 1.2The fission reaction: products, energy released and neutrons
  3. 1.3Microscopic and macroscopic cross-sections
  4. 1.4Fast, epithermal and thermal neutrons
  5. 1.5Multiplication factor and the four-factor formula
  6. 1.6Delayed neutrons and their role in control
  7. 1.7Moderators: light water, heavy water and graphite
  8. 1.8Neutron poisons: xenon-135 and samarium-149
  9. 1.9Decay heat after reactor shutdown
  10. 1.10Workshop: neutron balance of a simplified PWR core
  1. 2.1PWR and VVER pressurised water reactors
  2. 2.2BWR and ABWR boiling water reactors
  3. 2.3CANDU heavy water reactors
  4. 2.4AGR and HTGR gas-cooled reactors
  5. 2.5Sodium- and lead-cooled fast reactors
  6. 2.6Generation III+ designs: AP1000, EPR, APR1400
  7. 2.7Small modular reactors (SMR)
  8. 2.8GIF Generation IV systems
  9. 2.9Comparison of performance, safety and costs
  10. 2.10Case study: technology selection for a new site
  1. 3.1Point kinetics equations
  2. 3.2Reactivity, period and step response
  3. 3.3Temperature and void reactivity coefficients
  4. 3.4Control rods and their differential worth
  5. 3.5Chemical shim control using boric acid
  6. 3.6Load following and manoeuvrability
  7. 3.7Spatial xenon oscillations
  8. 3.8Start-up from subcritical and approach to criticality
  9. 3.9Reactor trip and safe shutdown
  10. 3.10Practical exercise: simulation of a power manoeuvre
  1. 4.1Reactor pressure vessel and internals
  2. 4.2Steam generators and pressuriser
  3. 4.3Reactor coolant pumps
  4. 4.4Chemical and volume control system
  5. 4.5Turbine, condenser and Rankine cycle
  6. 4.6Feedwater and feedwater heaters
  7. 4.7Essential service water systems
  8. 4.8Ventilation and effluent treatment
  9. 4.9P&ID diagrams of a reference plant
  10. 4.10Workshop: reading the primary circuit P&ID
  1. 5.1The INSAG-10 defence-in-depth principle
  2. 5.2Physical barriers against radioactive release
  3. 5.3Fundamental safety functions
  4. 5.4Single failure criterion and redundancy
  5. 5.5Diversity, physical separation and seismic classification
  6. 5.6Safety classification of structures and components
  7. 5.7Requirements of the IAEA SSR-2/1 series
  8. 5.8Human factors in control room design
  9. 5.9Lessons from Three Mile Island, Chernobyl and Fukushima
  10. 5.10Case study: barrier analysis for a loss of coolant
  1. 6.1Emergency core cooling system (ECCS)
  2. 6.2High- and low-pressure safety injection
  3. 6.3Auxiliary feedwater
  4. 6.4Passive heat removal systems
  5. 6.5Containment: design, isolation and spray
  6. 6.6Passive autocatalytic hydrogen recombiners
  7. 6.7Filtered containment venting
  8. 6.8Emergency power supply and diesel generators
  9. 6.9Post-Fukushima FLEX portable equipment
  10. 6.10Laboratory: ECCS response to a small LOCA
  1. 7.1Categories of initiating events
  2. 7.2Deterministic analysis of design basis accidents
  3. 7.3Loss of coolant accident (LOCA)
  4. 7.4Steam generator tube rupture
  5. 7.5Anticipated transients without scram (ATWS)
  6. 7.6Station blackout (total loss of AC power)
  7. 7.7Severe accidents and core melt phenomenology
  8. 7.8Severe accident management guidelines (SAMG)
  9. 7.9System codes: RELAP5 and TRACE
  10. 7.10Practical exercise: analysis of a loss of flow transient
  1. 8.1Operating organisation and operating shifts
  2. 8.2Technical specifications
  3. 8.3Normal and emergency operating procedures
  4. 8.4Symptom-based emergency operating procedures (EOP)
  5. 8.5Training and licensing of operating personnel
  6. 8.6Full-scope simulators
  7. 8.7Plant configuration management
  8. 8.8Control room communication and human error prevention
  9. 8.9Operating experience and WANO performance indicators
  10. 8.10Case study: managing an alarm during start-up
  1. 9.1Planning refuelling outages
  2. 9.2Preventive, predictive and corrective maintenance
  3. 9.3The 10 CFR 50.65 maintenance rule
  4. 9.4In-service inspection to ASME XI
  5. 9.5Surveillance testing of safety systems
  6. 9.6Work management and permits in controlled areas
  7. 9.7The ALARA criterion during outages
  8. 9.8Spare parts and obsolescence management
  9. 9.9Equipment reliability indicators
  10. 9.10Workshop: refuelling outage plan with dose optimisation
  1. 10.1Dosimetric quantities and units
  2. 10.2Classification of areas and exposed workers
  3. 10.3Personal and area dosimetry
  4. 10.4Source term and effluent monitoring
  5. 10.5Surface contamination control
  6. 10.6Shielding and dose rate calculation
  7. 10.7On-site emergency plan
  8. 10.8Environmental radiological monitoring of the site
  9. 10.9Management of operational waste
  10. 10.10Practical exercise: estimating collective dose for a maintenance job
  1. 11.1Operating licences and periodic safety reviews
  2. 11.2The safety analysis report and its updating
  3. 11.3The Spanish Nuclear Safety Council (CSN) and the Spanish framework
  4. 11.4Directive 2014/87/Euratom on nuclear safety
  5. 11.5WENRA reference levels
  6. 11.6Regulatory inspection and the oversight system
  7. 11.7Safety culture according to INSAG-4 and GSR Part 2
  8. 11.8Event reporting and the INES scale
  9. 11.9Root cause analysis of incidents
  10. 11.10Case study: assessment of a design modification
  1. 12.1Selection of the plant case and scope
  2. 12.2Literature review and applicable regulations
  3. 12.3Definition of hypotheses and analysis scenarios
  4. 12.4Neutronic or thermal-hydraulic modelling
  5. 12.5Assessment of safety margins
  6. 12.6Proposal for operational improvements
  7. 12.7Residual risk analysis
  8. 12.8Conclusions and future lines of work
  9. 12.9Master's Thesis report
  10. 12.10Master's Thesis: defence before a panel
Methodology, software & labs

How you'll learn

The programme is 100% online 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 you can combine it with your job.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is RELAP5, TRACE, MELCOR, SERPENT and MATLAB, in free, academic or evaluation versions. Practical work is based on real procedures: transient simulation on a full-scope simulator, analysis of real operating events and planning of a refuelling outage. Assessment is continuous for each module, plus the final Master's Thesis.

Standards covered: Directive 2014/87/Euratom, IAEA SSR-2/1 Safety of Nuclear Power Plants: Design, IAEA SSR-2/2 Safety of Nuclear Power Plants: Commissioning and Operation, IAEA SF-1 Fundamental Safety Principles, Real Decreto 1217/2024, 10 CFR Part 50, ASME BPVC Section XI, CSN Instruction IS-26.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of Directive 2014/87/Euratom, IAEA SSR-2/1 and IAEA SSR-2/2 applied to real cases, not as a theoretical annex.
Industry software:RELAP5, TRACE, MELCOR, SERPENT and MATLAB, in free, academic or evaluation versions.
Master's Thesis with defence:a safety and operational analysis of a nuclear power plant case, with neutronic or thermal-hydraulic modelling and assessment of safety margins, 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.

Neutron balance of a core
Calculate the neutron balance of a simplified PWR core.
Power manoeuvre simulation
Simulate a power manoeuvre and analyse the reactor's kinetic response.
Transient and LOCA analysis
Analyse ECCS response to a small LOCA and a loss of flow transient with system codes.
Outage plan with dose optimisation
Prepare a refuelling outage plan applying ALARA and estimating collective dose.
Master's Thesis
Safety and operational analysis of a real plant case with safety margin assessment, defended before a panel.
Career opportunities

Where this takes you

Nuclear operations engineerNuclear safety engineerControl room supervisorAccident analysis engineerLicensing technicianNuclear maintenance engineer
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's 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 RELAP5, TRACE, MELCOR, SERPENT 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 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.

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