151-2017-00L Nuclear Fuels and Materials
| Semester | Spring Semester 2018 |
| Lecturers | M. A. Pouchon, P. J.‑P. Spätig |
| Periodicity | yearly recurring course |
| Language of instruction | English |
| Abstract | Materials for nuclear power plants and fuel are discussed. The course is a basic introduction into this topic and it is mainly concerned with light water reactors. Structural materials for pressure boundaries (reactor pressure vessel, pipings) and reactor internals are introduced. Fuel and fuel claddings are also discussed. Main emphasize is on damage and degradation mechanisms during service. |
| Learning objective | The students know the most important structural materials in nuclear reactors know fuel and its behaviour in a reactor know important ageing and degradation mechanisms in nuclear power plants |
| Content | • Brief review of materials science basics • LWRs and their structural materials, damage mechanisms • Cladding materials, corrosion, failure modes • Pressure-boundary components, ageing, degradation • Structural integrity, surveillance, lifetime management • Structural materials for future advanced NPPs • General description of nuclear fuels, introduction to radiation damage • Fuel thermal performance • Fuel thermo-mechanical behaviour • Production, evolution of fission products • Fission gas release mechanisms • Fuel related safety limits • Advanced fuels for future NPPs |
| Literature | Distributed documents, recommended book chapters |
| Prerequisites / Notice | Prerequisite for: Advanced Topics in Nuclear Reactor Materials (2nd sem.) |