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CourseNuclear Engineering & Nuclear Fuel Cycle Technologies Applications open

Course in Simulation of Irradiated Materials Behaviour

Online 300-hour course in simulation of irradiated materials behaviour. 6 modules covering ASTM E185 (reactor pressure vessel surveillance programmes), ASTM E900 (embrittlement trend curve) and SRIM/TRIM. 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

Explain the mechanisms of irradiation damage in metals.

02

Calculate displacements per atom according to ASTM E693.

03

Analyse the embrittlement of pressure vessel steels.

04

Interpret surveillance programmes according to ASTM E185.

05

Model damage at atomic and mesoscale.

06

Evaluate the structural integrity of irradiated components.

07

Compare candidate materials for advanced fission and fusion.

Profile

Who it's for

  • Nuclear materials engineer wishing to specialise in Simulation of Irradiated Materials Behaviour.
  • Irradiation damage researcher wishing to specialise in Simulation of Irradiated Materials Behaviour.
  • Structural integrity engineer wishing to specialise in Simulation of Irradiated Materials Behaviour.
  • Fracture mechanics specialist wishing to specialise in Simulation of Irradiated Materials Behaviour.
  • Ageing management engineer wishing to specialise in Simulation of Irradiated Materials Behaviour.
  • Atomistic simulation analyst wishing to specialise in Simulation of Irradiated Materials Behaviour.
  • Graduates in engineering or science seeking to enter the nuclear industry.
Standards & tools

What you'll work with

  • ASTM E185 (reactor pressure vessel surveillance programmes)
  • ASTM E900 (embrittlement trend curve)
  • ASTM E693 (displacements per atom in steels)
  • ASTM E521 (neutron damage simulation with ions)
  • ASME BPVC Section XI (in-service inspection)
  • 10 CFR 50 Appendix G (fracture toughness requirements)
  • RCC-MRx (components for high-temperature and irradiation service)
Syllabus

6 modules · 300 h

  1. 1.1Displacement cascades and dpa
  2. 1.2NRT and arc-dpa models
  3. 1.3Point defects: vacancies and interstitials
  4. 1.4Recombination and defect sinks
  5. 1.5Transmutation and helium production
  6. 1.6Neutron spectrum and dose rate
  7. 1.7Neutron versus ion irradiation
  8. 1.8Resulting microstructure: loops and voids
  9. 1.9Materials for fission and fusion reactors
  10. 1.10Practice: estimating dpa with SRIM
  1. 2.1Hardening and embrittlement
  2. 2.2Shift of the ductile-to-brittle transition temperature
  3. 2.3Swelling from voids
  4. 2.4Irradiation-induced creep
  5. 2.5Irradiation growth in zirconium alloys
  6. 2.6Radiation-induced segregation
  7. 2.7Irradiation-assisted stress corrosion cracking
  8. 2.8Helium embrittlement
  9. 2.9Vessel surveillance according to ASTM E185
  10. 2.10Case study: RTNDT shift according to RG 1.99
  1. 3.1EAM and MEAM interatomic potentials
  2. 3.2Cascade simulation with LAMMPS
  3. 3.3Boundary conditions and thermostats
  4. 3.4Defect formation and migration energies
  5. 3.5Defect–dislocation interaction
  6. 3.6Machine-learning potentials
  7. 3.7First-principles calculations with DFT
  8. 3.8Time scales and limitations
  9. 3.9Defect analysis with OVITO
  10. 3.10Laboratory: 10 keV cascade in iron with LAMMPS
  1. 4.1Object kinetic Monte Carlo
  2. 4.2Reaction rate theory
  3. 4.3Cluster dynamics
  4. 4.4Discrete dislocation dynamics
  5. 4.5Phase-field modelling of precipitation
  6. 4.6Void evolution and swelling
  7. 4.7Hardening by the dispersed barrier model
  8. 4.8Coupling between scales
  9. 4.9MOOSE and MARMOT platforms
  10. 4.10Workshop: defect evolution by rate theory
  1. 5.1Phenomenology of the UO2 pellet
  2. 5.2Fission gas release
  3. 5.3Densification and swelling
  4. 5.4Pellet–cladding interaction
  5. 5.5High-burnup structure
  6. 5.6FRAPCON, TRANSURANUS and BISON codes
  7. 5.7Cladding corrosion and hydriding
  8. 5.8Behaviour under RIA and LOCA
  9. 5.9Accident-tolerant fuels
  10. 5.10Laboratory: power history with a fuel code
  1. 6.1Selection of material and problem
  2. 6.2Dose and spectrum estimation
  3. 6.3Atomistic simulation of defects
  4. 6.4Mesoscale evolution model
  5. 6.5Prediction of mechanical properties
  6. 6.6Comparison with experimental data
  7. 6.7Uncertainty analysis
  8. 6.8Design implications
  9. 6.9Report and presentation
  10. 6.10Final review with the tutor
Methodology, software & labs

How you'll learn

Fully 100 % online training on the SEIUM campus, with downloadable material, recorded classes and an assigned technical tutor. No fixed timetable: students progress at their own pace within the intake, which makes it compatible with work.

Each module combines theory, guided reading of the original standard and applied exercises. The working software is SRIM/TRIM, LAMMPS, ANSYS Mechanical, Abaqus, Python (NumPy), in free, academic or evaluation versions. Tests are studied using real procedures for Charpy tests on surveillance specimens, microstructural analysis of irradiated materials and irradiation damage calculations. Assessment is continuous by module plus the final integrating project.

Accredited 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 operational limits.
Industry-mentored:lecturers with careers 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 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 material and problem

Explain the mechanisms of irradiation damage in metals.

Dose and spectrum estimation

Calculate displacements per atom according to ASTM E693.

Atomistic simulation of defects

Analyse the embrittlement of pressure vessel steels.

Mesoscale evolution model

Interpret surveillance programmes according to ASTM E185.

Prediction of mechanical properties

Model damage at atomic and mesoscale.

Career opportunities

Where this takes you

Nuclear materials engineerIrradiation damage researcherStructural integrity engineerFracture mechanics specialistAgeing management engineerAtomistic simulation analyst
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.

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FAQ

Frequently asked questions

The programme totals 300 hours spread over 3 to 5 months. That is between 10 and 15 hours per week on average, compatible with a full-time job.

The course uses SRIM/TRIM, LAMMPS, ANSYS Mechanical, Abaqus, Python (NumPy). Free, academic or evaluation versions are used, and the tutor indicates the free alternative where one exists.

An own diploma from SEIUM on 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 are recognised in the advanced programme. Check the recognition policy when you enrol.

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