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Course in Pebble-Bed and Gas-Cooled Reactors

Online 300-hour course in pebble-bed and gas-cooled reactors. 6 modules covering ASME BPVC Section III, Division 5 (high-temperature and graphite reactors), NRC Regulatory Guide 1.232 (design criteria for non-LWR reactors) and Serpent. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesOctober / March
LocationEurope (Madrid)
AwardSEIUM Institute diploma
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Learning outcomes

What you will be able to do

01

Describe the concept of the gas-cooled pebble-bed reactor.

02

Analyse the thermal-hydraulics of the gaseous coolant in the core.

03

Explain neutronics and core management with continuous pebble recirculation.

04

Evaluate inherent safety characteristics and accident scenarios.

05

Identify the behaviour of graphite and TRISO fuel under irradiation.

06

Assess coolant chemistry, materials and operating experience.

07

Prepare a technical study on a gas-cooled high-temperature reactor.

Profile

Who it's for

  • High-temperature reactor engineer wishing to specialise in Pebble-Bed and Gas-Cooled Reactors.
  • Gas thermal-hydraulics analyst wishing to specialise in Pebble-Bed and Gas-Cooled Reactors.
  • Graphite materials engineer wishing to specialise in Pebble-Bed and Gas-Cooled Reactors.
  • TRISO fuel specialist wishing to specialise in Pebble-Bed and Gas-Cooled Reactors.
  • Advanced reactor safety engineer wishing to specialise in Pebble-Bed and Gas-Cooled Reactors.
  • Generation IV reactor researcher wishing to specialise in Pebble-Bed and Gas-Cooled Reactors.
  • Graduates in engineering or science seeking to enter Generation IV reactors.
Standards & tools

What you'll work with

  • ASME BPVC Section III, Division 5 (high-temperature and graphite reactors)
  • NRC Regulatory Guide 1.232 (design criteria for non-LWR reactors)
  • ASTM D7219 (specification for isotropic nuclear graphite)
  • ASTM D7301 (nuclear graphite for high fluence)
  • KTA 3102 series standards (core design of high-temperature reactors)
  • IAEA SSR-2/1 (Rev.1) (design of nuclear power plants)
Syllabus

6 modules · 300 h

  1. 1.1Direct-cycle principle
  2. 1.2Essential differences from pressurised water
  3. 1.3Pressure vessel, steam separators and dryers
  4. 1.4Internal and external recirculation pumps
  5. 1.5Recirculation flow as a control means
  6. 1.6Bottom-entry control rods
  7. 1.7Pressure suppression containment
  8. 1.8Design evolution and generations
  9. 1.9Technology-specific terminology
  10. 1.10Exercise: tracing the steam path
  1. 2.1Subcooled and saturated boiling
  2. 2.2Void fraction and its axial distribution
  3. 2.3Two-phase flow and flow regimes
  4. 2.4Pressure losses in the channel
  5. 2.5Dryout boiling crisis and associated margin
  6. 2.6Critical power correlations
  7. 2.7Flow distribution between channels
  8. 2.8Channel stability and oscillations
  9. 2.9Neutronic and thermal-hydraulic coupling
  10. 2.10Practice: calculating the void profile of a channel
  1. 3.1Effect of voids on moderation
  2. 3.2Negative void coefficient and its role
  3. 3.3Axial power distribution and its control
  4. 3.4Rod patterns and withdrawal sequences
  5. 3.5Fuel management and refuelling
  6. 3.6Fuel with integral burnable poisons
  7. 3.7Thermal and linear power limits
  8. 3.8On-line margin monitoring
  9. 3.9Power oscillations and their suppression
  10. 3.10Practice: designing a rod sequence
  1. 4.1Emergency coolant injection
  2. 4.2Automatic depressurisation
  3. 4.3Main steam isolation
  4. 4.4Alternative shutdown system and liquid poison
  5. 4.5Pressure suppression and pool
  6. 4.6Loss-of-coolant sequences
  7. 4.7Station blackout
  8. 4.8Hydrogen generation and filtered venting
  9. 4.9Severe accident management
  10. 4.10Practice: analysing an accident sequence
  1. 5.1Direct-cycle water chemistry
  2. 5.2Carry-over of impurities to the turbine
  3. 5.3Activation and radiation in the steam circuit
  4. 5.4Radiation protection in the turbine hall
  5. 5.5Stress corrosion cracking in internals
  6. 5.6Hydrogen and noble metal injection
  7. 5.7In-service inspection of the vessel and internals
  8. 5.8Ageing management
  9. 5.9Operating experience of the technology
  10. 5.10Practice: chemistry and surveillance plan
  1. 6.1Choice of reference plant
  2. 6.2Description of the design and its systems
  3. 6.3Thermal-hydraulic analysis of a channel
  4. 6.4Thermal margin analysis
  5. 6.5Core management strategy
  6. 6.6Analysis of an accident sequence
  7. 6.7Chemistry and materials programme
  8. 6.8Improvement proposals
  9. 6.9Technical report
  10. 6.10Project defence
Methodology, software & labs

How you'll learn

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

Each module combines theory, guided reading of the original standard and applied exercises. The working software is Serpent, MCNP, Flownex, OpenFOAM, in free, academic or evaluation versions. Tests are studied using real thermal-hydraulic analysis procedures for pebble beds, studies of TRISO fuel behaviour, and a review of operating experience from the AVR, THTR and HTR-PM reactors. Assessment is continuous, module by module, plus the final integrating project.

Accreditable laboratories(EN ISO/IEC 17025) with rotor rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-oriented final project:safety case, test plan, compliance dossier and operating limits.
Industry mentoring:lecturers with a track record 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 OT cyber-security, 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.

Choice of reference plant

Describe the concept of the gas-cooled pebble-bed reactor.

Description of the design and its systems

Analyse the thermal-hydraulics of the gaseous coolant in the core.

Thermal-hydraulic analysis of a channel

Explain neutronics and core management with continuous pebble recirculation.

Thermal margin analysis

Evaluate inherent safety characteristics and accident scenarios.

Core management strategy

Identify the behaviour of graphite and TRISO fuel under irradiation.

Career opportunities

Where this takes you

High-temperature reactor engineerGas thermal-hydraulics analystGraphite materials engineerTRISO fuel specialistAdvanced reactor safety engineerGeneration IV reactor researcher
Admissions & scholarships

Requirements

  • No prior degree is required.
  • Internet connection and a computer capable of running the programme software.
  • Spanish at a level sufficient to follow technical standards 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 a week, compatible with full-time work.

The course uses Serpent, MCNP, Flownex and OpenFOAM. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

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

Yes. Modules passed in a course or Postgraduate Diploma in the same area are recognised in the advanced programme. Check the recognition policy when you enrol.

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