CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Course in Nuclear Transient Modelling

Online course of 300 h in nuclear transient modelling. 6 modules covering 10 CFR 50.46 (emergency core cooling system acceptance criteria), Regulatory Guide 1.203 (transient and accident analysis methods) and RELAP5-3D. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesSet by the faculty
AwardSEIUM Institute certificate
Virtual lab · try it before you enrol

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SIM · LIVE ●
Learning outcomes

What you will be able to do

01

Describe the coupled neutronic and thermal-hydraulic dynamics of the reactor.

02

Model transient thermal-hydraulic phenomena in two-phase circuits.

03

Build plant nodalisations in system codes.

04

Analyse reactivity and loss-of-flow transients.

05

Evaluate loss-of-coolant accidents against acceptance criteria.

06

Apply best-estimate methodologies with uncertainty quantification.

07

Produce a complete transient analysis with discussion of results.

Profile

Who it's for

  • Transient and accident analyst looking to specialise in Nuclear Transient Modelling.
  • Nuclear thermal-hydraulics engineer looking to specialise in Nuclear Transient Modelling.
  • Nuclear safety engineer looking to specialise in Nuclear Transient Modelling.
  • Licensing engineer looking to specialise in Nuclear Transient Modelling.
  • Plant model developer looking to specialise in Nuclear Transient Modelling.
  • Safety assessor in a regulatory body looking to specialise in Nuclear Transient Modelling.
  • Engineering or science graduates seeking to enter nuclear power plants.
Standards & tools

What you'll work with

  • 10 CFR 50.46 (emergency core cooling system acceptance criteria)
  • Regulatory Guide 1.203 (transient and accident analysis methods)
  • IAEA SSG-2 Rev.1 (deterministic safety analysis)
  • 10 CFR 50, Appendix K (ECCS evaluation models)
  • Regulatory Guide 1.157 (ECCS best-estimate calculations)
  • NUREG-0800, Chapter 15 (transient and accident analysis)
  • IAEA GSR Part 4 Rev.1 (safety assessment of facilities)
Syllabus

6 modules · 300 h

  1. 1.1Point kinetics equations
  2. 1.2Delayed neutrons and precursor groups
  3. 1.3Reactivity, period and inhour equation
  4. 1.4Prompt jump and prompt criticality
  5. 1.5Feedbacks: Doppler, moderator and void
  6. 1.6Fuel thermal time constants
  7. 1.7Spatial kinetics and the quasi-static method
  8. 1.8Xenon and samarium effects
  9. 1.9Transient classification by frequency
  10. 1.10Practical: point kinetics with feedback in Python
  1. 2.1Conservation equations in two-phase flow
  2. 2.2Homogeneous, drift-flux and two-fluid models
  3. 2.3Heat transfer and boiling crisis
  4. 2.4DNBR and CPR as thermal criteria
  5. 2.5Transient conduction in the pellet
  6. 2.6Pellet-cladding gap and its evolution
  7. 2.7Natural circulation
  8. 2.8Density wave instabilities in BWRs
  9. 2.9Pump and valve models
  10. 2.10Workshop: loss-of-flow transient in a channel
  1. 3.1Structure of RELAP5 and TRACE
  2. 3.2Nodalisation of a primary circuit
  3. 3.3Component and control models
  4. 3.4Neutronic-thermal-hydraulic coupling
  5. 3.5PARCS and its coupling with system codes
  6. 3.6CATHARE and ATHLET codes
  7. 3.7Steady-state initialisation
  8. 3.8Convergence criteria and time step
  9. 3.9Common user errors
  10. 3.10Laboratory: simplified nodalisation in RELAP5
  1. 4.1Control rod ejection (RIA)
  2. 4.2Rod drop and uncontrolled withdrawal
  3. 4.3Inadvertent boron dilution
  4. 4.4Forced flow loss
  5. 4.5Pump rotor locking
  6. 4.6Steam line break and overcooling
  7. 4.7ATWS: transient without reactor trip
  8. 4.8Fuel acceptance criteria
  9. 4.9OECD/NEA transient benchmarks
  10. 4.10Case study: analysis of a control rod ejection
  1. 5.1Phenomenology of a large LOCA
  2. 5.2Critical discharge and initial depressurisation
  3. 5.3Core refilling and reflooding
  4. 5.410 CFR 50.46 acceptance criteria
  5. 5.5Small LOCA and controlled depressurisation
  6. 5.6Integral experiments LOFT and PKL
  7. 5.7BEPU approach and CSAU methodology
  8. 5.8Scaling and facility similarity
  9. 5.9Severe accidents: overview with MELCOR
  10. 5.10Laboratory: small LOCA with a system code
  1. 6.1Selection of the transient and the plant
  2. 6.2Assumptions and initial conditions
  3. 6.3Construction of the calculation model
  4. 6.4Running the base case
  5. 6.5Parametric sensitivity analysis
  6. 6.6Verification of acceptance criteria
  7. 6.7Uncertainty quantification
  8. 6.8Discussion of safety margins
  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 assigned technical tutor. No fixed timetables: students progress at their own pace within the intake, which makes it possible to combine with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is RELAP5-3D, TRACE, CATHARE, ATHLET, PARCS, in free, academic or evaluation versions. Tests are studied using real transient simulation procedures with system codes, comparison with integral experimental facilities, and best-estimate uncertainty analysis. Assessment is continuous per module plus the final integrating project.

Accreditable laboratories(EN ISO/IEC 17025) with rotor test rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-driven Master's Thesis:safety case, test plan, compliance dossier and operating limits.
Industry mentorship: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, cyber-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.

Selection of the transient and the plant

Describe the coupled neutronic and thermal-hydraulic dynamics of the reactor.

Assumptions and initial conditions

Model transient thermal-hydraulic phenomena in two-phase circuits.

Construction of the calculation model

Build plant nodalisations in system codes.

Running the base case

Analyse reactivity and loss-of-flow transients.

Parametric sensitivity analysis

Evaluate loss-of-coolant accidents against acceptance criteria.

Career opportunities

Where this takes you

Transient and accident analystNuclear thermal-hydraulics engineerNuclear safety engineerLicensing engineerPlant model developerSafety assessor in a regulatory body
Admissions & scholarships

Requirements

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

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 is 300 hours in total, spread over 3 to 5 months. That is an average of between 10 and 15 hours per week, compatible with a full-time job.

You will work with RELAP5-3D, TRACE, CATHARE, ATHLET and PARCS. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

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

Yes. Modules passed in a course or postgraduate diploma in the same area can be credited towards the higher programme. Check the recognition policy when you enrol.

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