Master’s in Reactor Thermal-Hydraulics and Transients Engineering
Online master's programme of 1,900 hours in reactor thermal-hydraulics and transients engineering, structured in 12 modules covering applied thermodynamics, fuel heat transfer, single- and two-phase flow, boiling crisis, subchannel and system analysis, operational transients, LOCA, severe accidents, nuclear CFD and uncertainty quantification, with an assigned technical tutor.
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
Apply thermodynamics and heat transfer to the reactor core.
Model two-phase flow and the boiling crisis.
Calculate thermal margins through subchannel analysis.
Nodalise primary circuits in system codes.
Analyse operational transients and loss of coolant accidents.
Assess severe accident phenomena with integral codes.
Quantify uncertainties according to BEPU methodologies.
Who it's for
- Thermal-hydraulics engineers looking to deepen their transient analysis skills.
- Transient analysts working with system codes.
- Accident analysis engineers.
- Nuclear CFD specialists.
- Fuel safety engineers.
- Thermal-hydraulics researchers.
- Engineering or science graduates seeking to enter nuclear engineering firms.
What you'll work with
- 10 CFR 50.46 (acceptance criteria for emergency core cooling systems)
- 10 CFR Part 50 Appendix K (required features of ECCS evaluation models)
- Regulatory Guide 1.203 Transient and Accident Analysis Methods (US NRC guidance on transient and accident analysis methods)
- IAEA SSG-2 Deterministic Safety Analysis for Nuclear Power Plants (IAEA guide on deterministic safety analysis)
- NUREG-0800 Chapter 15 (US NRC review plan for transient and accident analyses)
- ANSI/ANS-51.1 (nuclear safety criteria for the design of PWR plants)
- IAPWS-IF97 (industrial formulation for the thermodynamic properties of water and steam)
- RELAP5
- TRACE
- CATHARE
- COBRA-TF
- OpenFOAM
12 modules · 1900 h
1.1Water properties and IAPWS-IF97 tables1.2Rankine cycles in nuclear power plants1.3Efficiency and regeneration1.4Brayton cycles for gas reactors1.5Supercritical CO2 cycles1.6Exergy and cycle losses1.7Plant energy balance1.8Conservation equations in control volumes1.9Properties of alternative coolants1.10Workshop: heat balance of a PWR plant
2.1Volumetric heat generation in the pellet2.2UO2 conductivity and its degradation with burnup2.3Gap conductance2.4Cladding and pellet centreline temperature2.5Axial temperature profiles2.6Thermal transients in the fuel rod2.7Fuel melting and limits2.8Accident tolerant fuels2.9FRAPCON and TRANSURANUS models2.10Practical exercise: radial temperature profile in a fuel rod
3.1Hydrodynamics in ducts and rod bundles3.2Two-phase flow regimes3.3Homogeneous and drift-flux models3.4Void fraction and slip3.5Two-fluid model3.6Two-phase pressure drop3.7Critical flow and choking3.8Density wave instabilities3.9Countercurrent flow and CCFL3.10Laboratory: vertical flow regime map
4.1The boiling curve4.2Onset of nucleate boiling4.3Subcooled boiling in hot channels4.4Critical heat flux and DNB4.5Film dryout in BWRs4.6W-3 correlation and Groeneveld look-up tables4.7Rewetting and Leidenfrost temperature4.8Mixing factors and separators4.9DNBR and MCPR margins4.10Practical exercise: MCPR calculation in a BWR bundle
5.1The subchannel concept5.2Turbulent mixing and cross-flow5.3Modelling with the COBRA-TF code5.4Modelling with the VIPRE code5.5Hot channel and uncertainty factors5.6Spacer and mixing grids5.7Effect of fuel rod deformation5.8Validation with PSBT and BFBT tests5.9Coupling with core calculation5.10Workshop: subchannel model of a 17×17 fuel assembly
6.1Nodalisation of the primary circuit6.2Pressuriser dynamics6.3Steam generators during transients6.4Pumps: homologous curves6.5Natural circulation and reflux6.6Boron and temperature mixing in the downcomer6.7Pressurised thermal shock6.8Containment: pressure and temperature6.9Interaction between primary and secondary circuits6.10Practical exercise: nodalisation of a four-loop PWR in RELAP5
7.1Classification of transients according to ANS7.2Loss of load and turbine trip7.3Loss of forced flow7.4Loss of feedwater7.5Excess steam extraction7.6Inadvertent opening of relief valves7.7BWR transients: MSIV closure7.8ATWS and system response7.9Analysis with safety margins7.10Case study: turbine trip without bypass
8.1Phases of a large LOCA8.2Blowdown, refill and reflood8.3Small and medium LOCA8.4Interfacing LOCA in low-pressure systems8.5ECCS acceptance criteria8.6Cladding oxidation and hydrogen generation8.7Sump recirculation and strainer blockage8.8LOFT, LSTF and PKL experimental facilities8.9BEPU and CSAU methodology8.10Laboratory: simulation of a small LOCA in TRACE
9.1Core heat-up and degradation9.2Corium formation9.3In-vessel retention and external cooling9.4Vessel failure and ex-vessel phenomena9.5Molten core-concrete interaction9.6Hydrogen combustion and mitigation9.7Containment behaviour9.8MELCOR, MAAP and ASTEC codes9.9Lessons from Fukushima Daiichi9.10Practical exercise: station blackout sequence with MELCOR
10.1RANS equations and turbulence models10.2LES and DNS in nuclear applications10.3Meshing of fuel bundles10.4Mixing in plenums and downcomer10.5Thermal fatigue due to stratification10.6Boron dilution with CFD10.7CFD-system code coupling10.8OECD/NEA best practice guidelines10.9Validation of CFD models10.10Workshop: thermal mixing in a T-junction with OpenFOAM
11.1Code validation matrices11.2Scaling effects11.3GRS and Wilks uncertainty methods11.4Quantification of input parameters11.5Wilks' formula and 95/95 tolerance11.6Global sensitivity analysis11.7The OECD BEMUSE project11.8Documentation for licensing11.9Calculation quality assurance11.10Case study: 95/95 analysis of peak cladding temperature
12.1Selection of the transient or accident12.2Definition of hypotheses and initial conditions12.3Nodalisation and model12.4Base case calculation12.5Sensitivity analysis12.6Uncertainty quantification12.7Assessment against acceptance criteria12.8Conclusions and recommendations12.9Master's Thesis report12.10Master's Thesis: defence before a panel
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, CATHARE, COBRA-TF and OpenFOAM, in free, academic or evaluation versions. Practical work is based on real procedures: transient simulation with system codes, subchannel analysis of a fuel assembly and a BEPU-type uncertainty study. Assessment is continuous for each module, plus the final Master's Thesis.
Standards covered: 10 CFR 50.46, 10 CFR Part 50 Appendix K, Regulatory Guide 1.203 Transient and Accident Analysis Methods, IAEA SSG-2 Deterministic Safety Analysis for Nuclear Power Plants, NUREG-0800 Chapter 15, ANSI/ANS-51.1, IAPWS-IF97.
Build it end to end
Your final project follows the real engineering workflow, step by step, reviewed by your tutor.
Where this takes you
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.
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, CATHARE, COBRA-TF and OpenFOAM, 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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