CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Course in Corrosion under Irradiation in Reactors

Online 300-hour course in corrosion under irradiation in reactors. 6 modules covering ASME BPVC Section XI (in-service inspection), NUREG-1801 (GALL report on ageing management) and Thermo-Calc. Assigned tutor and open enrolment.

Duration300 h
ModeOnline
Start datesSet by the faculty
AwardSEIUM Institute certificate
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Learning outcomes

What you will be able to do

01

Describe the irradiation environment and its effects on corrosion.

02

Explain irradiation-assisted corrosion mechanisms.

03

Identify the most affected components and materials.

04

Select appropriate testing and characterisation techniques.

05

Interpret IASCC and oxidation test results.

06

Propose mitigation measures and life management strategies.

07

Prepare a degradation assessment report for a component.

Profile

Who it's for

  • Nuclear materials engineer looking to specialise in Corrosion under Irradiation in Reactors.
  • Corrosion specialist looking to specialise in Corrosion under Irradiation in Reactors.
  • Ageing management engineer looking to specialise in Corrosion under Irradiation in Reactors.
  • Researcher in irradiated materials looking to specialise in Corrosion under Irradiation in Reactors.
  • Internals integrity engineer looking to specialise in Corrosion under Irradiation in Reactors.
  • Materials laboratory technician looking to specialise in Corrosion under Irradiation in Reactors.
  • Graduates in engineering or sciences seeking to join nuclear power plants.
Standards & tools

What you'll work with

  • ASME BPVC Section XI (in-service inspection)
  • NUREG-1801 (GALL report on ageing management)
  • ASTM E521 (neutron damage simulation with charged particles)
  • ASTM G2/G2M (corrosion of zirconium alloys in water at 360 °C)
  • IAEA SSG-48 (ageing management in nuclear power plants)
  • EPRI MRP-227 (inspection of PWR internals)
Syllabus

6 modules · 300 h

  1. 1.1Neutron flux and spectrum in a power reactor
  2. 1.2Displacement damage and its measurement
  3. 1.3Point defects and their evolution
  4. 1.4Displacement cascades and recombination
  5. 1.5Transmutation and compositional change
  6. 1.6Water radiolysis and species generated
  7. 1.7Oxidants and reductants in the coolant
  8. 1.8Electrochemical corrosion potential
  9. 1.9Difference between corrosion with and without irradiation
  10. 1.10Exercise: relating flux to accumulated damage
  1. 2.1Irradiation-assisted stress corrosion cracking
  2. 2.2Element segregation at grain boundaries
  3. 2.3Irradiation hardening and deformation localisation
  4. 2.4Chromium depletion at grain boundaries
  5. 2.5Role of the corrosion potential
  6. 2.6Dose threshold for susceptibility
  7. 2.7Effect of applied and residual stress
  8. 2.8Crack initiation versus propagation
  9. 2.9Propagation rate and its measurement
  10. 2.10Practice: interpreting crack growth data
  1. 3.1Reactor pressure vessel internals and bolting
  2. 3.2Guide tubes and core structures
  3. 3.3Welds and heat-affected zones
  4. 3.4Nickel alloys and their behaviour
  5. 3.5Irradiated austenitic stainless steels
  6. 3.6Boiling water reactor components
  7. 3.7Operating experience of real failures
  8. 3.8Inspection criteria by component
  9. 3.9Risk-based prioritisation
  10. 3.10Practice: prioritising components for inspection
  1. 4.1Hot-cell testing with irradiated material
  2. 4.2Compact specimens and crack growth tests
  3. 4.3Slow strain rate tensile tests
  4. 4.4Ion simulation and its limitations
  5. 4.5Transmission electron microscopy
  6. 4.6Chemical analysis of grain boundaries
  7. 4.7Electrochemical potential measurement
  8. 4.8Recirculating autoclaves
  9. 4.9Comparability between laboratories
  10. 4.10Practice: designing a testing programme
  1. 5.1Hydrogen injection and noble metal chemistry
  2. 5.2Corrosion potential control
  3. 5.3Reduction of weld residual stresses
  4. 5.4Surface treatments and shot peening
  5. 5.5Replacement with more resistant materials
  6. 5.6In-service inspection and applicable techniques
  7. 5.7Integrity assessment with an accepted crack
  8. 5.8Acceptance criteria and defect analysis
  9. 5.9Ageing management programmes
  10. 5.10Practice: assessing the remaining life of a component
  1. 6.1Selection of the component and its conditions
  2. 6.2Estimation of accumulated irradiation damage
  3. 6.3Identification of active mechanisms
  4. 6.4Compilation of materials data
  5. 6.5Structural integrity assessment
  6. 6.6Mitigation proposal
  7. 6.7In-service inspection plan
  8. 6.8Estimation of remaining life
  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 a assigned technical tutor. No fixed timetables: students progress at their own pace within the enrolment period, 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 Thermo-Calc, SRIM/TRIM, OLI Studio, COMSOL Multiphysics, in free, academic or evaluation versions. Tests are studied using real autoclave procedures with irradiation in a research reactor, irradiation-assisted stress corrosion cracking (IASCC) tests, and oxide layer microscopy. Assessment is continuous, module by module, plus the final integrative project.

Accreditable laboratories(EN ISO/IEC 17025) with a rotor test rig, EMC/Lightning pre-compliance, HIL/SIL, vibration/acoustics.
Evidence-oriented Master's Thesis:safety case, test plan, compliance dossier and operating 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, OT cybersecurity, DIH and compliance as 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 component and its conditions

Describe the irradiation environment and its effects on corrosion.

Estimation of accumulated irradiation damage

Explain irradiation-assisted corrosion mechanisms.

Identification of active mechanisms

Identify the most affected components and materials.

Compilation of materials data

Select appropriate testing and characterisation techniques.

Structural integrity assessment

Interpret IASCC and oxidation test results.

Career opportunities

Where this takes you

Nuclear materials engineerCorrosion specialistAgeing management engineerResearcher in irradiated materialsInternals integrity engineerMaterials laboratory technician
Admissions & scholarships

Requirements

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

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 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.

The programme uses Thermo-Calc, SRIM/TRIM, OLI Studio and COMSOL Multiphysics. Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

An in-house SEIUM diploma 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 recognised towards the advanced programme. Check the recognition policy when you enrol.

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