Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Nuclear Safety and Probabilistic Risk Assessment Engineering

Online master's programme of 1,900 hours in nuclear safety engineering and probabilistic risk analysis, structured in 12 modules covering safety principles, applied reliability, event and fault trees, human reliability analysis, Level 1, 2 and 3 PSA, internal and external hazards, PSA applications, modelling tools and complementary deterministic safety, with an assigned technical tutor.

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

What you will be able to do

01

Understand safety principles and the deterministic and probabilistic approaches.

02

Apply reliability techniques and Bayesian statistics to components.

03

Build event trees and fault trees for safety systems.

04

Quantify human error with recognised methods.

05

Develop Level 1, 2 and 3 PSA and their uncertainty analyses.

06

Assess fire, flooding and seismic risks.

07

Use PSA in risk-informed decision-making.

Profile

Who it's for

  • PSA analysts looking to deepen their modelling and quantification skills.
  • Nuclear safety engineers who want to integrate probabilistic methods into their work.
  • Human reliability specialists.
  • External hazards engineers working on fire, flooding or seismic analysis.
  • Regulatory risk assessors.
  • Risk analysis consultants.
  • Engineering or science graduates seeking to enter the nuclear power sector.
Standards & tools

What you'll work with

  • IAEA SSG-3 Development and Application of Level 1 PSA (IAEA guide on Level 1 probabilistic safety assessment)
  • IAEA SSG-4 Development and Application of Level 2 PSA (IAEA guide on Level 2 probabilistic safety assessment)
  • ASME/ANS RA-S-1.4-2021 (PRA standard for advanced non-LWR nuclear power plants)
  • Regulatory Guide 1.200 (technical adequacy of PRA results for risk-informed activities)
  • Regulatory Guide 1.174 (use of PRA in risk-informed decisions on licensing basis changes)
  • IAEA SF-1 Fundamental Safety Principles (IAEA fundamental safety principles)
  • NUREG/CR-6850 (fire PRA methodology for nuclear power facilities)
  • CSN Instruction IS-25 (Spanish requirements on probabilistic safety assessments)
  • RiskSpectrum PSA
  • SAPHIRE
  • CAFTA
  • MELCOR
  • MACCS
Syllabus

12 modules · 1900 h

  1. 1.1The IAEA fundamental safety objective
  2. 1.2The ten principles of SF-1
  3. 1.3Risk, hazard and social acceptability
  4. 1.4Quantitative safety objectives
  5. 1.5Deterministic versus probabilistic approach
  6. 1.6Defence in depth and its five levels
  7. 1.7Classification of events by frequency
  8. 1.8Safety margin and conservatism
  9. 1.9Risk-informed decision-making
  10. 1.10Case study: safety objectives of different regulators
  1. 2.1Probability theory and Boolean algebra
  2. 2.2Exponential, Weibull and lognormal distributions
  3. 2.3Failure rate and the bathtub curve
  4. 2.4Component availability and unavailability
  5. 2.5Failures on demand and failures during operation
  6. 2.6Bayesian parameter inference
  7. 2.7Reliability databases: NUREG/CR-6928 and ZEDB
  8. 2.8Test and repair times
  9. 2.9Uncertainty propagation
  10. 2.10Practical exercise: Bayesian estimation of a failure rate
  1. 3.1Internal initiating events
  2. 3.2Initiating event frequencies
  3. 3.3Safety functions and success criteria
  4. 3.4Building event trees
  5. 3.5Accident sequences and end states
  6. 3.6Functional and systemic event trees
  7. 3.7Thermal-hydraulic analysis of success criteria
  8. 3.8Dependencies between headings
  9. 3.9Grouping into plant damage states
  10. 3.10Workshop: event tree for a loss of feedwater
  1. 4.1Fault tree logic
  2. 4.2Modelling of safety systems
  3. 4.3Minimal cut sets
  4. 4.4Common cause failures: beta and alpha models
  5. 4.5Latent failures and periodic testing
  6. 4.6Unavailability due to maintenance
  7. 4.7Support dependencies: electrical and cooling
  8. 4.8Quantification and truncation
  9. 4.9Model review and documentation
  10. 4.10Laboratory: fault tree of the safety injection system
  1. 5.1Human error and its classification
  2. 5.2Pre- and post-initiator actions
  3. 5.3THERP and ASEP methods
  4. 5.4The SPAR-H method and its multipliers
  5. 5.5CBDT and HCR/ORE methods
  6. 5.6Performance shaping factors
  7. 5.7Dependencies between human actions
  8. 5.8Analysis of available time
  9. 5.9Integration into the PSA
  10. 5.10Practical exercise: SPAR-H quantification of a recovery action
  1. 6.1Scope and structure of Level 1 PSA
  2. 6.2Core damage frequency
  3. 6.3Integration of event trees and fault trees
  4. 6.4Importance measures: Fussell-Vesely and RAW
  5. 6.5Sensitivity and uncertainty analysis
  6. 6.6The ASME/ANS RA-S standard
  7. 6.7PSA quality according to RG 1.200
  8. 6.8Shutdown and low power PSA
  9. 6.9PSA peer reviews
  10. 6.10Case study: quantification of a simplified PSA model
  1. 7.1Severe accident progression
  2. 7.2Containment event trees
  3. 7.3Containment failure modes
  4. 7.4Large early release frequency
  5. 7.5Source term and release categories
  6. 7.6Phenomenology: DCH, steam explosion and hydrogen
  7. 7.7Atmospheric dispersion and consequences
  8. 7.8Individual and societal risk
  9. 7.9MELCOR, MAAP and MACCS codes
  10. 7.10Workshop: release categorisation for a dry containment
  1. 8.1Fire analysis to NUREG/CR-6850
  2. 8.2Internal flooding analysis
  3. 8.3Seismic: fragility curves and PSHA
  4. 8.4Seismic margin and SMA
  5. 8.5External flooding and meteorological phenomena
  6. 8.6Events affecting multiple units
  7. 8.7Spent fuel pool risks
  8. 8.8European stress tests
  9. 8.9Lessons from Fukushima for PSA
  10. 8.10Case study: impact of a fire in a cable spreading room
  1. 9.1Real-time risk monitor
  2. 9.2Configuration and on-line maintenance
  3. 9.3Risk-informed technical specifications
  4. 9.4Risk-informed in-service inspection
  5. 9.5Component categorisation according to 10 CFR 50.69
  6. 9.6Event significance assessment
  7. 9.7The Reactor Oversight Process (ROP)
  8. 9.8Prioritisation of design modifications
  9. 9.9Integrated decision-making to RG 1.174
  10. 9.10Practical exercise: risk assessment of a maintenance configuration
  1. 10.1Architecture of RiskSpectrum PSA
  2. 10.2Modelling in SAPHIRE
  3. 10.3Management of reliability databases
  4. 10.4Uncertainty analysis with Monte Carlo
  5. 10.5Dynamic PSA and DET methods
  6. 10.6Reliability of passive systems
  7. 10.7Reliability of safety software
  8. 10.8Models of digital I&C systems
  9. 10.9Integration with deterministic analyses
  10. 10.10Laboratory: building a model in SAPHIRE
  1. 11.1Design basis accident analysis
  2. 11.2Design extension conditions
  3. 11.3Single failure and acceptance criteria
  4. 11.4Severe accident analysis
  5. 11.5BEPU best-estimate methodology
  6. 11.6Periodic safety review
  7. 11.7Stress tests and margins
  8. 11.8Ageing management and risk
  9. 11.9Communicating risk to the public
  10. 11.10Case study: deterministic-probabilistic integration of a modification
  1. 12.1Selection of the scope of the analysis
  2. 12.2Collection of plant information
  3. 12.3Initiating events model
  4. 12.4System and human reliability models
  5. 12.5Quantification and results
  6. 12.6Importance and uncertainty analysis
  7. 12.7Risk reduction proposals
  8. 12.8Study conclusions
  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 RiskSpectrum PSA, SAPHIRE, CAFTA, MELCOR and MACCS, in free, academic or evaluation versions. Practical work is based on real procedures: development of a simplified Level 1 PSA, risk assessment of maintenance configurations and review of seismic fragilities. Assessment is continuous for each module, plus the final Master's Thesis.

Standards covered: IAEA SSG-3 Development and Application of Level 1 PSA, IAEA SSG-4 Development and Application of Level 2 PSA, ASME/ANS RA-S-1.4-2021, Regulatory Guide 1.200, Regulatory Guide 1.174, IAEA SF-1 Fundamental Safety Principles, NUREG/CR-6850, CSN Instruction IS-25.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of IAEA SSG-3, IAEA SSG-4 and ASME/ANS RA-S-1.4-2021 applied to real cases, not as a theoretical annex.
Industry software:RiskSpectrum PSA, SAPHIRE, CAFTA, MELCOR and MACCS, in free, academic or evaluation versions.
Master's Thesis with defence:a plant PSA study covering initiating events, system and human reliability models, quantification and risk reduction proposals, 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.

Bayesian failure rate estimation
Estimate component failure rates using Bayesian inference.
Event and fault trees
Build an event tree for a loss of feedwater and the fault tree of the safety injection system.
Human reliability quantification
Quantify a recovery action using SPAR-H and integrate it into the PSA.
Maintenance configuration risk
Assess the risk of a maintenance configuration with a SAPHIRE model.
Master's Thesis
PSA study of a plant with quantification, importance analysis and risk reduction proposals, defended before a panel.
Career opportunities

Where this takes you

PSA analystNuclear safety engineerHuman reliability specialistExternal hazards engineerRegulatory risk assessorRisk analysis consultant
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 RiskSpectrum PSA, SAPHIRE, CAFTA, MELCOR and MACCS, 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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