Postgraduate DiplomaDefense, Military Engineering & Land Systems Applications open

Diploma in Radiation-Resistant Alloys

Online postgraduate diploma of 800 hours in radiation-resistant alloys. 8 modules covering radiation damage in metals, irradiation degradation mechanisms, vessel and internals steels, zirconium and nickel alloys, advanced resistant materials, post-irradiation characterisation (ASTM E185-21, 10 CFR 50 Appendix H) and multiscale damage modelling, with an assigned technical tutor.

Duration6–8 months
ModeOnline
LanguageEnglish
Start datesSet by the faculty
AwardSEIUM Institute diploma

Diploma in Radiation-Resistant Alloys — studying from Malta

Malta's defence sector is comparatively small, reflecting the country's neutrality and modest armed forces. Activity centres on the Armed Forces of Malta, maritime surveillance, border security and the associated technical support. Engineering roles are mostly found in equipment maintenance, communications, infrastructure and government procurement rather than large-scale defence manufacturing. Professionals may find opportunities through public service and contractors supplying the armed forces and related agencies, where reliability and compliance with national procurement rules are important.

Fees for Malta: €1,090 (Euro), with instalments and employer sponsorship available.

Relevant bodies in Malta

  • Armed Forces of Malta
  • Ministry for Home Affairs, National Security and Law Enforcement
  • Department of Contracts (Malta)
  • Malta Standards Authority (MSA)

Typical roles

  • Military Systems Engineer
  • Defence Equipment Maintenance Engineer
  • Procurement Engineer
  • Communications Systems Engineer

Questions from Malta

Which bodies regulate defence and military engineering work in Malta?

Malta's Armed Forces and the Ministry responsible for defence oversee military engineering and procurement. General engineering practice is regulated by the Chamber of Engineers (KSU) under the Engineering Profession Act. Export and dual-use controls follow EU and national rules. A SEIUM qualification is private and not accredited, so any recognition depends on employers or the relevant authority.

What career paths exist in Malta for land systems and defence engineering?

Opportunities in Malta are limited and mostly within government, the Armed Forces and their suppliers, with more substantial defence industry work typically found abroad. Many roles require security clearance and specific experience. A private qualification can support your profile, but you should expect employers to focus on experience and clearance eligibility.

How do I study this from Malta, and what should I consider about workload and funding?

The programme is delivered fully online in English, with an assigned technical tutor and a final project. You do not need a visa to study from home in Malta. Durations range from 300 to 1,900 hours, so plan time alongside any work commitments. Ask about instalment payments and whether employer sponsorship is available.

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Learning outcomes

What you will be able to do

01

Understand radiation damage mechanisms in metals and alloys.

02

Calculate displacements per atom in different irradiation environments.

03

Assess the embrittlement of vessel steels through surveillance programmes.

04

Analyse the in-service behaviour of zirconium and nickel alloys.

05

Select advanced materials for new-generation and fusion reactors.

06

Interpret post-irradiation characterisation results.

07

Apply multiscale modelling tools to irradiation damage.

Profile

Who it's for

  • Nuclear materials engineers working on plant components and new reactor designs.
  • Reactor vessel integrity specialists running surveillance programmes.
  • Radiation damage researchers in fission and fusion materials.
  • Fuel and cladding engineers working with zirconium alloys.
  • Hot cell laboratory technicians characterising irradiated specimens.
  • Ageing management analysts assessing long-term operation.
  • Engineering or science graduates seeking to enter the nuclear power sector.
Standards & tools

What you'll work with

  • ASTM E185-21 (design of surveillance programmes for light-water reactor vessels)
  • 10 CFR 50 Appendix H (US reactor vessel material surveillance requirements)
  • Regulatory Guide 1.99 Rev. 2 (radiation embrittlement of reactor vessel materials)
  • ASTM E2215 (evaluation of surveillance capsules)
  • ASTM E521 (neutron radiation damage simulation by charged-particle irradiation)
  • ASTM E693 (characterising neutron exposures in iron and low-alloy steels in dpa)
  • 10 CFR 50.46 (acceptance criteria for emergency core cooling systems)
  • ASME BPVC Section III (rules for construction of nuclear facility components)
  • SRIM/TRIM
  • LAMMPS
  • MOOSE
  • Thermo-Calc
  • Abaqus
Syllabus

8 modules

  1. 1.1Displacement cascades and dpa
  2. 1.2NRT model of atomic displacements
  3. 1.3Vacancies, interstitials and their clusters
  4. 1.4Recombination and absorption at sinks
  5. 1.5Transmutation and helium production
  6. 1.6Fast and thermal neutron spectra
  7. 1.7Ion irradiation as a surrogate technique
  8. 1.8Damage calculation with SRIM
  9. 1.9Time and length scales of damage
  10. 1.10Practical exercise: calculating dpa profiles with SRIM
  1. 2.1Hardening and embrittlement
  2. 2.2Transition temperature shift
  3. 2.3Void swelling
  4. 2.4Irradiation creep
  5. 2.5Radiation-induced segregation
  6. 2.6Irradiation growth in zirconium
  7. 2.7Helium embrittlement
  8. 2.8Irradiation-assisted stress corrosion cracking
  9. 2.9Phase instability and precipitation
  10. 2.10Case study: analysis of surveillance Charpy curves
  1. 3.1SA-508 and SA-533 ferritic steels
  2. 3.2Influence of copper, nickel and phosphorus
  3. 3.3304 and 316 austenitic stainless steels
  4. 3.4Reactor vessel surveillance programmes
  5. 3.5RG 1.99 embrittlement correlations
  6. 3.6Thermal annealing of vessels
  7. 3.79–12% Cr ferritic-martensitic steels
  8. 3.8Eurofer97 reduced-activation steels
  9. 3.9Welds and heat-affected zones
  10. 3.10Workshop: estimating end-of-life RTNDT
  1. 4.1Zircaloy-2, Zircaloy-4 and ZIRLO
  2. 4.2Zr-Nb and M5 alloys
  3. 4.3Hydriding and hydride reorientation
  4. 4.4Oxidation in high-temperature water
  5. 4.5Nickel alloys 600 and 690
  6. 4.6Inconel X-750 and 718 in springs and bolting
  7. 4.7Embrittlement of nickel alloys
  8. 4.8Behaviour in a loss-of-coolant accident
  9. 4.910 CFR 50.46 acceptance criteria
  10. 4.10Lab: metallography of oxidised cladding
  1. 5.1Oxide dispersion strengthened (ODS) steels
  2. 5.2High-entropy alloys
  3. 5.3Vanadium and tungsten alloys for fusion
  4. 5.4SiC/SiC composites
  5. 5.5Interfaces as defect sinks
  6. 5.6Nanostructuring and grain boundaries
  7. 5.7Accident-tolerant FeCrAl alloys
  8. 5.8Materials for Generation IV reactors
  9. 5.9Selection for sodium-cooled fast reactors
  10. 5.10Case study: candidate cladding materials for a fast reactor
  1. 6.1TEM microscopy of loops and voids
  2. 6.2Atom probe tomography
  3. 6.3Nanoindentation of irradiated layers
  4. 6.4Miniaturised tensile and Charpy specimens
  5. 6.5Neutron and X-ray diffraction
  6. 6.6Hot cells and remote handling
  7. 6.7Positron annihilation spectroscopy
  8. 6.8ASTM E185 and E2215 standards
  9. 6.9Traceability of irradiated specimens
  10. 6.10Practical exercise: interpreting TEM images of irradiation damage
  1. 7.1Molecular dynamics of cascades
  2. 7.2EAM interatomic potentials
  3. 7.3Kinetic Monte Carlo of defects
  4. 7.4Cluster dynamics and rate theory
  5. 7.5Dislocations and crystal plasticity
  6. 7.6Finite elements with irradiated properties
  7. 7.7MOOSE framework for nuclear materials
  8. 7.8Validation with experimental data
  9. 7.9Uncertainty quantification
  10. 7.10Lab: simulating a cascade with LAMMPS
  1. 8.1Definition of the component and environment
  2. 8.2Review of irradiation databases
  3. 8.3Selection of candidate alloys
  4. 8.4Estimate of accumulated damage
  5. 8.5Prediction of end-of-life properties
  6. 8.6Irradiation and test plan
  7. 8.7Risk and margin analysis
  8. 8.8Justified technical recommendation
  9. 8.9Report and presentation
  10. 8.10Final project: final review with the tutor
Methodology, software & labs

How you'll learn

The programme is delivered 100% online 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 you can combine it with your job.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is SRIM/TRIM, LAMMPS, MOOSE, Thermo-Calc and Abaqus, in free, academic or evaluation versions. Testing is studied through real procedures for Charpy testing of surveillance specimens, ion irradiation in accelerators and TEM characterisation in hot cells. Assessment is continuous by module, plus the final project.

Standards covered: ASTM E185-21, 10 CFR 50 Appendix H, Regulatory Guide 1.99 Rev. 2, ASTM E2215, ASTM E521, ASTM E693, 10 CFR 50.46, ASME BPVC Section III.

Assigned technical tutor:every module ends with a deliverable that your tutor marks individually.
Standards-based learning:guided reading of ASTM E185-21, 10 CFR 50 Appendix H and Regulatory Guide 1.99 Rev. 2 applied to real cases, not as a theoretical annex.
Industry software:SRIM/TRIM, LAMMPS, MOOSE, Thermo-Calc and Abaqus, in free, academic or evaluation versions.
Final project:A radiation-resistant alloys project covering the component environment, candidate alloy selection, accumulated damage, end-of-life properties, irradiation and test plan, and a justified technical recommendation, 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.

Component and environment
Define the component and its irradiation environment.
Candidate alloys
Review irradiation databases and select candidate alloys.
Damage estimate
Estimate accumulated damage in dpa with SRIM and predict end-of-life properties.
Irradiation and test plan
Draw up an irradiation and post-irradiation test plan with risk and margin analysis.
Final project
Develop a complete project with a justified technical recommendation on the alloy to use.
Career opportunities

Where this takes you

Nuclear materials engineerReactor vessel integrity specialistRadiation damage researcherFuel and cladding engineerHot cell laboratory technicianAgeing management analyst
Admissions & scholarships

Requirements

  • Prior technical training or professional experience in the sector. No university degree is required.
  • An internet connection and a computer able to run the programme's 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 SRIM/TRIM, LAMMPS, MOOSE, Thermo-Calc and Abaqus, 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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