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Course in Nuclear Reactor Thermal-Hydraulics

Online 300-hour course in nuclear reactor thermal-hydraulics. 6 modules covering IAEA SSG-2 Rev. 1 (deterministic safety analysis), 10 CFR 50.46 (ECCS acceptance criteria) and RELAP5-3D. Personal tutor assigned and enrolment open.

Duration300 h
ModeOnline
Start datesOctober / March
LocationEurope (Madrid)
AwardSEIUM Institute diploma
Enrol now View syllabus Ask an advisor
Virtual lab · try it before you enrol

Take the controls.

Run a real engineering trade-off from this programme. Move the sliders, watch the model react in real time and beat the challenge.

SIM · LIVE ●
Learning outcomes

What you will be able to do

01

Apply mass, energy and momentum balances to the core.

02

Analyse two-phase flow, boiling and boiling crisis.

03

Carry out subchannel analysis of the core.

04

Model reactor systems with system codes.

05

Simulate transients and loss-of-coolant accidents.

06

Assess thermal safety margins.

07

Develop a complete thermal-hydraulic analysis project.

Profile

Who it's for

  • Nuclear thermal-hydraulics engineer who wants to specialise in Nuclear Reactor Thermal-Hydraulics.
  • Reactor safety analyst who wants to specialise in Nuclear Reactor Thermal-Hydraulics.
  • Accident analysis engineer who wants to specialise in Nuclear Reactor Thermal-Hydraulics.
  • Core design engineer who wants to specialise in Nuclear Reactor Thermal-Hydraulics.
  • Nuclear CFD specialist who wants to specialise in Nuclear Reactor Thermal-Hydraulics.
  • Two-phase flow researcher who wants to specialise in Nuclear Reactor Thermal-Hydraulics.
  • Graduates in engineering or science seeking to enter the nuclear industry.
Standards & tools

What you'll work with

  • IAEA SSG-2 Rev. 1 (deterministic safety analysis)
  • 10 CFR 50.46 (ECCS acceptance criteria)
  • NRC Regulatory Guide 1.203 (EMDAP)
  • IAEA SSG-56 (reactor cooling system design)
  • NUREG-0800, Chapter 15 (transient and accident analysis)
  • ASME V&V 20 (verification and validation in CFD and heat transfer)
Syllabus

6 modules · 300 h

  1. 1.1Heat generation in the fuel
  2. 1.2Conduction in the pellet and cladding
  3. 1.3Conductivity integral and centreline temperature
  4. 1.4Pellet-cladding gap conductance
  5. 1.5Single-phase forced convection in subchannels
  6. 1.6Dittus-Boelter and Weisman correlations
  7. 1.7Pressure drops in the core
  8. 1.8Hot channel factors
  9. 1.9Axial temperature distribution
  10. 1.10Practice: temperature profile in a fuel rod
  1. 2.1Two-phase flow regimes
  2. 2.2Quality, void fraction and slip
  3. 2.3Drift-flux model
  4. 2.4Subcooled and nucleate boiling
  5. 2.5Critical heat flux: DNB and dryout
  6. 2.6W-3 correlations and Groeneveld tables
  7. 2.7Two-phase pressure drop
  8. 2.8Density wave instabilities
  9. 2.9Critical flow in blowdowns
  10. 2.10Workshop: DNBR calculation in a channel
  1. 3.1Subchannel formulation
  2. 3.2Turbulent mixing and cross-flow
  3. 3.3Spacer grids and mixing vanes
  4. 3.4COBRA-TF and VIPRE codes
  5. 3.5Modelling PWR fuel assemblies
  6. 3.6BWR modelling and void fraction
  7. 3.7Coupling with neutronic calculation
  8. 3.8Thermal design limits
  9. 3.9Validation with PSBT experiments
  10. 3.10Laboratory: subchannel model with CTF
  1. 4.1PWR primary circuit
  2. 4.2Steam generators and pressuriser
  3. 4.3BWR recirculation
  4. 4.4Natural circulation in the primary circuit
  5. 4.5Emergency cooling systems
  6. 4.6Passive cooling in AP1000 and SMRs
  7. 4.7Containment thermal-hydraulics
  8. 4.8Sodium- and gas-cooled reactors
  9. 4.9Molten salt reactors
  10. 4.10Case study: natural circulation in NuScale
  1. 5.1System codes: RELAP5 and TRACE
  2. 5.2Large and small loss-of-coolant accidents (LOCA)
  3. 5.3Loss of flow and rotor blockage
  4. 5.4Steam generator tube rupture
  5. 5.5Anticipated transients without scram (ATWS)
  6. 5.610 CFR 50.46 criteria
  7. 5.7Three Mile Island accident
  8. 5.8Loss of power at Fukushima
  9. 5.9CFD in nuclear thermal-hydraulics
  10. 5.10Practice: SBLOCA simulation with RELAP5
  1. 6.1Definition of the reactor and scenario
  2. 6.2Collection of design data
  3. 6.3Model construction
  4. 6.4Steady-state calculation
  5. 6.5Transient simulation
  6. 6.6Assessment of thermal margins
  7. 6.7Sensitivity analysis
  8. 6.8Safety conclusions
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

100% online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. No fixed timetables: students progress at their own pace within the intake, which makes it possible to combine the course with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is RELAP5-3D, TRACE, CTF (COBRA-TF), ANSYS CFX, OpenFOAM, in free, academic or evaluation versions. Tests are studied using real procedures for subchannel analysis, LOCA and transient simulation, and calculation of margins to DNB. Assessment is continuous by module, plus the final integrative project.

Accredited laboratories(EN ISO/IEC 17025) with a rotor rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-oriented final project:safety case, test plan, compliance dossier and operational limits.
Industry mentoring:lecturers with experience in training, , eVTOL/UAM and flight test.
Flexible format(hybrid/online), international cohorts and support from SEIUM Career Services.
Ethics and safety:safety-by-design approach, with ciber-OT, DIH and compliance as its pillars.
Capstone project

Build it end to end

Your final project follows the real engineering workflow, step by step, reviewed by your tutor.

Definition of the reactor and scenario

Apply mass, energy and momentum balances to the core.

Collection of design data

Analyse two-phase flow, boiling and boiling crisis.

Model construction

Carry out subchannel analysis of the core.

Steady-state calculation

Model reactor systems with system codes.

Transient simulation

Simulate transients and loss-of-coolant accidents.

Career opportunities

Where this takes you

Nuclear thermal-hydraulics engineerReactor safety analystAccident analysis engineerCore design engineerNuclear CFD specialistTwo-phase flow researcher
Admissions & scholarships

Requirements

  • No previous degree is required.
  • Internet connection and a computer capable of running the programme's software.
  • Sufficient Spanish to follow technical regulatory reading.

Ready to start?

Send your application today. Our admissions team replies within 72 hours with your study plan and funding options.

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FAQ

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 work with RELAP5-3D, TRACE, CTF (COBRA-TF), ANSYS CFX and OpenFOAM. Free, academic or evaluation versions are used, and the tutor indicates the open-source alternative where one exists.

An own diploma from SEIUM upon passing the continuous assessment and the integrative project. It is in-house training, not an official Ministry qualification.

Yes. Modules passed in a course or postgraduate diploma in the same area are credited towards the advanced programme. Check the credit transfer policy when you enrol.

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