Apply now
Master'sNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Master’s in Materials under Irradiation and Radiation Damage Engineering

Online master's programme of 1,900 hours in materials under irradiation and radiation damage engineering. 12 modules covering radiation-solid interaction, defect evolution, microstructural changes, mechanical properties, vessel steels, internals, zirconium alloys, fusion and Generation IV materials and multiscale modelling, with ASTM E900, ASTM E185 and LAMMPS, with an assigned technical tutor.

Duration1900 h
ModeOnline
LanguageEnglish
Start datesSet by the faculty
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

Explain the interaction of radiation with solids.

02

Model the evolution of irradiation-induced defects.

03

Relate microstructural changes to mechanical properties.

04

Predict the embrittlement of reactor vessel steels.

05

Assess materials for advanced and fusion reactors.

06

Design irradiation and characterisation campaigns.

07

Apply structural integrity methods with irradiated properties.

Profile

Who it's for

  • Nuclear materials engineers.
  • Radiation damage researchers.
  • Structural integrity specialists.
  • Reactor vessel surveillance engineers.
  • Materials modelling scientists.
  • Hot cell technicians looking to broaden their expertise.
  • Engineering or science graduates seeking to enter the nuclear power industry.
Standards & tools

What you'll work with

  • ASTM E900 (embrittlement trend prediction for vessel steels)
  • ASTM E185 (reactor vessel surveillance programmes)
  • ASTM E1921 (master curve and reference temperature T0)
  • ASTM E693 (dpa characterisation of neutron exposure)
  • 10 CFR Part 50 Appendix H (reactor vessel material surveillance requirements)
  • ASME BPVC Section XI (in-service inspection and flaw evaluation)
  • RCC-MRx (design rules for high-temperature and research reactor components)
  • Regulatory Guide 1.99 (radiation embrittlement of vessel materials)
  • LAMMPS
  • VASP
  • SRIM
  • Abaqus
  • OVITO
Syllabus

12 modules · 1900 h

  1. 1.1Types of incident radiation
  2. 1.2Energy transfer and elastic collisions
  3. 1.3Threshold displacement energy
  4. 1.4Kinchin-Pease and NRT models
  5. 1.5Displacements per atom (dpa)
  6. 1.6Transmutation reactions
  7. 1.7Helium and hydrogen production
  8. 1.8Neutron spectra and PKA
  9. 1.9Correlation between irradiation sources
  10. 1.10Workshop: dpa calculation with SPECTRA-PKA
  1. 2.1Vacancies and interstitials
  2. 2.2Displacement cascades
  3. 2.3Defect recombination and diffusion
  4. 2.4Dislocation loops
  5. 2.5Cavities and bubbles
  6. 2.6Rate theory
  7. 2.7Sinks and dislocation bias
  8. 2.8Molecular dynamics of cascades
  9. 2.9Kinetic Monte Carlo
  10. 2.10Practical exercise: simulation of a cascade with LAMMPS
  1. 3.1Radiation-induced segregation
  2. 3.2Radiation-induced precipitation and dissolution
  3. 3.3Amorphisation of ceramic phases
  4. 3.4Copper- and manganese-rich clusters
  5. 3.5G-phases and precipitates in steels
  6. 3.6Grain boundary evolution
  7. 3.7Stability of ODS nanoprecipitates
  8. 3.8Microstructure of irradiated zirconium alloys
  9. 3.9Characterisation techniques
  10. 3.10Laboratory: analysis of TEM images of dislocation loops
  1. 4.1Irradiation hardening
  2. 4.2Embrittlement and transition temperature shift
  3. 4.3Loss of ductility
  4. 4.4Dislocation channelling
  5. 4.5Irradiation creep
  6. 4.6Void swelling
  7. 4.7High-temperature helium embrittlement
  8. 4.8Fatigue under irradiation
  9. 4.9Toughness of irradiated materials
  10. 4.10Case study: Charpy curve before and after irradiation
  1. 5.1Composition and microstructure
  2. 5.2Influence of copper, nickel and phosphorus
  3. 5.3Embrittlement prediction models
  4. 5.4Surveillance programmes
  5. 5.5Master curve and T0
  6. 5.6Vessel annealing
  7. 5.7Flux and fluence effects
  8. 5.8Experience with long-service vessels
  9. 5.9Assessment for LTO
  10. 5.10Practical exercise: prediction of ΔT41J according to ASTM E900
  1. 6.1Swelling in 304 and 316 steels
  2. 6.2Irradiation-assisted stress corrosion cracking (IASCC)
  3. 6.3Stress relaxation in bolts
  4. 6.4Embrittlement of internals
  5. 6.5Management of internals according to MRP-227
  6. 6.6Steels for fast reactors
  7. 6.715-15Ti and D9 steels
  8. 6.8Experience in inspecting internals
  9. 6.9Mitigation and replacement
  10. 6.10Case study: assessment of baffle bolts
  1. 7.1Irradiation growth
  2. 7.2Cladding creep
  3. 7.3Hardening and ductility
  4. 7.4Hydrogen and hydrides under irradiation
  5. 7.5Effects on corrosion
  6. 7.6Advanced zirconium alloys
  7. 7.7Behaviour in accidents
  8. 7.8Halden data
  9. 7.9Constitutive models for irradiated cladding
  10. 7.10Workshop: axial growth model of a guide tube
  1. 8.1Reduced-activation ferritic-martensitic steels
  2. 8.2Oxide dispersion strengthened steels
  3. 8.3Vanadium alloys
  4. 8.4Tungsten for plasma-facing components
  5. 8.5SiC/SiC ceramic composites
  6. 8.6Graphite in high-temperature reactors
  7. 8.7Materials in molten salts
  8. 8.8Materials in liquid metals
  9. 8.9The IFMIF-DONES facility in Granada
  10. 8.10Case study: materials selection for a sodium-cooled reactor
  1. 9.1Materials test reactors
  2. 9.2Ion irradiation
  3. 9.3Hot cell testing
  4. 9.4Miniature specimens and small-scale testing
  5. 9.5Nanoindentation of irradiated layers
  6. 9.6TEM and APT microscopy
  7. 9.7Neutron and X-ray diffraction
  8. 9.8Positrons and SANS
  9. 9.9Irradiation dosimetry
  10. 9.10Laboratory: design of an ion irradiation campaign
  1. 10.1First-principles DFT
  2. 10.2Development of interatomic potentials
  3. 10.3Molecular dynamics of defects
  4. 10.4Object kinetic Monte Carlo
  5. 10.5Cluster dynamics
  6. 10.6Dislocation dynamics
  7. 10.7Crystal plasticity models
  8. 10.8Finite elements with irradiated properties
  9. 10.9European modelling projects
  10. 10.10Practical exercise: vacancy formation energy calculation with DFT
  1. 11.1Fracture mechanics with irradiation
  2. 11.2Pressurised thermal shock
  3. 11.3Assessment according to ASME XI
  4. 11.4RCC-MRx codes for high temperature
  5. 11.5Creep-fatigue interaction
  6. 11.6Safety factors
  7. 11.7Ageing management
  8. 11.8LTO and high fluences
  9. 11.9Regulatory review of assessments
  10. 11.10Case study: PTS margin at 60 years
  1. 12.1Selection of the material and problem
  2. 12.2State-of-the-art review
  3. 12.3Design of the experimental or numerical methodology
  4. 12.4Data acquisition
  5. 12.5Microstructural analysis of results
  6. 12.6Correlation with properties
  7. 12.7Design implications
  8. 12.8Conclusions and future work
  9. 12.9Master's Thesis report
  10. 12.10Master's Thesis: defence before a panel
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: you progress at your own pace within each intake, making it compatible with full-time work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is LAMMPS, VASP, SRIM, Abaqus and OVITO, in free, academic or evaluation versions. Tests are studied using real procedures for characterising irradiated materials, multiscale simulation of defects and assessing reactor vessel embrittlement. Assessment is continuous for each module, plus the final Master's Thesis.

Standards covered: ASTM E900, ASTM E185, ASTM E1921, ASTM E693, 10 CFR Part 50 Appendix H, ASME BPVC Section XI, RCC-MRx and Regulatory Guide 1.99.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of ASTM E900, ASTM E185 and ASTM E1921 applied to real cases, not as a theoretical annex.
Industry software:LAMMPS, VASP, SRIM, Abaqus and OVITO, in free, academic or evaluation versions.
Master's Thesis with defence:an experimental or numerical study of an irradiated material, correlating microstructure with properties and design implications, defended before a panel.
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.

Damage dose calculation
You calculate dpa for a component using SPECTRA-PKA.
Cascade simulation
You simulate a displacement cascade with LAMMPS and analyse the resulting defects.
Embrittlement prediction
You predict the ΔT41J shift of a vessel steel according to ASTM E900.
PTS margin assessment
You assess the pressurised thermal shock margin of a vessel at 60 years.
Master's Thesis
An experimental or numerical study of an irradiated material correlating microstructure with properties and design implications, defended before a panel.
Career opportunities

Where this takes you

Nuclear materials engineerRadiation damage researcherStructural integrity specialistReactor vessel surveillance engineerMaterials modelling scientistHot cell technician
Admissions & scholarships

Requirements

  • A university degree in engineering, science or architecture, or equivalent demonstrable professional experience.
  • 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.

Apply now Scholarships
FAQ

Frequently asked questions

The programme totals 1,900 hours over 12–14 months. You set your own pace within each intake, and your tutor helps you plan the workload around your job.

You work with LAMMPS, VASP, SRIM, Abaqus and OVITO, 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 Master's Thesis. 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 in a course or postgraduate diploma in the same area are recognised in the higher programme. Ask about the recognition policy when you enrol.

A university degree in engineering, science or architecture (or equivalent professional experience), a computer able to run the programme 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.

Keep exploring

Related programmes

See all in Nuclear Engineering & Nuclear Fuel Cycle Technologies
Master's11,090 $

Master’s in Accelerators, Radiation Sources and Isotope Production Engineering

Online master's programme of 1,900 hours in accelerator engineering, radiation sources and isotope production. 12 modules covering accelerator physics, medical cyclotrons, reactor and cyclotron isotope production,…

1900 hOnlineNuclear Engineering & Nuclear Fuel Cycle Technologies
Master's11,090 $

Master’s in Radioactive Waste Management and Deep Geological Disposal Engineering

Online master's programme of 1,900 hours in radioactive waste management and deep geological disposal engineering. 12 modules covering waste origin and classification, predisposal management, disposal concepts,…

1900 hOnlineNuclear Engineering & Nuclear Fuel Cycle Technologies
Master's11,090 $

Master’s in Monte Carlo and Radiation Transport Engineering

Online master's programme of 1,900 hours in Monte Carlo and radiation transport engineering, structured in 12 modules covering Monte Carlo statistics, neutron and photon transport, variance…

1900 hOnlineNuclear Engineering & Nuclear Fuel Cycle Technologies
Master’s in Materials under Irradiation and Radiation Damage EngineeringEnrol
Related programmes

More in Nuclear Engineering & Nuclear Fuel Cycle Technologies

Master’s in Industrial Process Heat from Nuclear Engineering (H₂, Ammonia, e-Fuels)View programme →Master’s in Decommissioning, Decontamination and Clearance (D&D) EngineeringView programme →Master’s in Corrosion, SCC and Chemical Compatibility Engineering in Primary CircuitsView programme →Master’s in Regulatory Compliance, QA/QM (ASME/ISO/IEC) and Auditing EngineeringView programme →Master’s in Data, Modelling & Simulation EngineeringView programme →Master’s in Fuel, Materials & Corrosion EngineeringView programme →

All Nuclear Engineering & Nuclear Fuel Cycle Technologies programmes → · How to apply · Fees & financing · Scholarships

Scroll to Top
SEIUM – Institute of Advanced Engineering
Powered by  GDPR Cookie Compliance
Privacy Overview

This website uses cookies so that we can provide you with the best user experience possible. Cookie information is stored in your browser and performs functions such as recognising you when you return to our website and helping our team to understand which sections of the website you find most interesting and useful.