Postgraduate DiplomaDefense, Military Engineering & Land Systems Applications open

Diploma in Two-Phase Flow in Nuclear Circuits

Online postgraduate diploma of 800 hours in two-phase flow in nuclear circuits. 8 modules covering two-phase flow fundamentals, flow patterns, two-phase pressure drop, boiling and heat transfer, instabilities, thermal-hydraulic system codes and safety applications, with an assigned technical tutor.

Duration6–8 months
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 the quantities and models of two-phase flow.

02

Identify flow patterns in tubes and rod bundles.

03

Calculate two-phase pressure drops with validated correlations.

04

Assess boiling margins and critical heat flux.

05

Analyse instabilities and special phenomena.

06

Use thermal-hydraulic system codes.

07

Apply two-phase analysis to reactor safety.

Profile

Who it's for

  • Thermal-hydraulic engineers.
  • Nuclear safety analysts.
  • System code specialists.
  • Multiphase flow researchers.
  • Fuel design engineers.
  • Licensing engineers.
  • Engineering or science graduates seeking to enter the nuclear energy sector.
Standards & tools

What you'll work with

  • 10 CFR 50.46 (ECCS acceptance criteria)
  • IAPWS-IF97 (thermodynamic properties of water and steam)
  • IAEA SSG-2 (deterministic safety analysis)
  • NUREG-0800 (Standard Review Plan, Chapter 15)
  • IAEA SRS-52 (best estimate plus uncertainty)
  • CSN Instruction IS-27 (design criteria)
  • RELAP5
  • TRACE
  • CATHARE
  • ANSYS Fluent
  • Python CoolProp
Syllabus

8 modules

  1. 1.1Definitions: void fraction and quality
  2. 1.2Superficial velocities
  3. 1.3Slip between phases
  4. 1.4Thermodynamic properties of water
  5. 1.5IAPWS-IF97 steam tables
  6. 1.6Conservation equations
  7. 1.7Homogeneous model
  8. 1.8Separated flow model
  9. 1.9Drift-flux model
  10. 1.10Workshop: void fraction calculation with the drift-flux model
  1. 2.1Patterns in vertical tubes
  2. 2.2Patterns in horizontal tubes
  3. 2.3Baker and Taitel-Dukler maps
  4. 2.4Bubbly and slug flow
  5. 2.5Annular flow
  6. 2.6Transitions between patterns
  7. 2.7Rod bundles
  8. 2.8Experimental visualisation
  9. 2.9Flow pattern instrumentation
  10. 2.10Lab: identification of patterns in an experimental loop
  1. 3.1Two-phase multipliers
  2. 3.2Lockhart-Martinelli correlation
  3. 3.3Friedel correlation
  4. 3.4Local (form) losses
  5. 3.5Acceleration pressure drop
  6. 3.6Gravitational gradient
  7. 3.7Flow through spacer grids
  8. 3.8Validation with data
  9. 3.9Uncertainty of correlations
  10. 3.10Practical exercise: pressure drop in a fuel channel
  1. 4.1The boiling curve
  2. 4.2Nucleate boiling
  3. 4.3Subcooled boiling
  4. 4.4Critical heat flux
  5. 4.5CHF correlations and Groeneveld look-up tables
  6. 4.6DNBR margin
  7. 4.7Film boiling and reflood
  8. 4.8Condensation
  9. 4.9Dryout in BWRs
  10. 4.10Case study: margin to critical heat flux in a PWR
  1. 5.1Density wave instability
  2. 5.2Ledinegg instability
  3. 5.3Oscillations in BWRs
  4. 5.4Critical flow and choking
  5. 5.5Water hammer and condensation
  6. 5.6Natural circulation
  7. 5.7Counter-current flow limitation (CCFL)
  8. 5.8Separators and dryers
  9. 5.9Droplet entrainment
  10. 5.10Practical exercise: stability analysis of a channel
  1. 6.1The two-fluid model
  2. 6.2RELAP5 and TRACE
  3. 6.3CATHARE
  4. 6.4System nodalisation
  5. 6.5Wall and heat transfer models
  6. 6.6LOCA simulation
  7. 6.7Scaling and integral experiments
  8. 6.8OECD/NEA programmes
  9. 6.9BEPU methodologies
  10. 6.10Lab: nodalisation of a circuit in RELAP5
  1. 7.1Loss-of-coolant accident
  2. 7.210 CFR 50.46 acceptance criteria
  3. 7.3Loss of flow
  4. 7.4Steam generator transients
  5. 7.5Passive cooling systems
  6. 7.6Multiphase CFD approaches
  7. 7.7Experimental validation
  8. 7.8CSN requirements
  9. 7.9Lessons from Three Mile Island
  10. 7.10Case study: analysis of a small-break LOCA
  1. 8.1System definition
  2. 8.2Model selection
  3. 8.3Pressure drop calculation
  4. 8.4Heat transfer
  5. 8.5Stability
  6. 8.6Simulation with a system code
  7. 8.7Uncertainty analysis
  8. 8.8Conclusions
  9. 8.9Report and presentation
  10. 8.10Final project: final review with the tutor
Methodology, software & labs

How you'll learn

100% online programme 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 the programme fits around your job.

Each module combines theory, guided reading of the original standard and applied exercises. You work with RELAP5, TRACE, CATHARE, ANSYS Fluent and Python CoolProp, in free, academic or evaluation versions. Practical work is based on real procedures: two-phase loop experiments, circuit nodalisation with system codes and analysis of margins to critical heat flux. Assessment is continuous by module, plus the final project.

Standards covered: 10 CFR 50.46, IAPWS-IF97, IAEA SSG-2, NUREG-0800, IAEA SRS-52 and CSN Instruction IS-27.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of 10 CFR 50.46, IAPWS-IF97 and IAEA SSG-2 applied to real cases, not as a theoretical annex.
Industry software:RELAP5, TRACE, CATHARE, ANSYS Fluent and Python CoolProp, in free, academic or evaluation versions.
Final project:a complete two-phase flow study of a nuclear circuit, from model selection and pressure drop to stability, system-code simulation and uncertainty analysis, reviewed by your tutor.
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.

Define the system
Define the nuclear circuit and select the appropriate two-phase models.
Calculate pressure drop
Calculate two-phase pressure drop with validated correlations.
Assess heat transfer and stability
Evaluate heat transfer margins and the stability of the system.
Simulate with a system code
Model the circuit in a system code and analyse the uncertainty of the results.
Final project
Present the conclusions in a report, reviewed by your tutor.
Career opportunities

Where this takes you

Thermal-hydraulic engineerNuclear safety analystSystem code specialistMultiphase flow researcherFuel design engineerLicensing engineer
Admissions & scholarships

Requirements

  • Prior technical training or professional experience in the sector. No university degree is required.
  • 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 800 hours over 6–8 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, ANSYS Fluent and Python CoolProp, 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 final project. 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 are recognised in a higher programme in the same area (postgraduate diploma or master's). Ask about the recognition policy when you enrol.

Prior technical training or professional experience in the sector (no university degree required), 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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