Understanding and mitigating ageing in nuclear power plants: materials and operational aspects of plant life management (PLiM)

Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC), along with their relevantanalysis and mitigation paths, as well as reactor-type specific plant life management (PLiM) practices. Obsolescence and other less obvious ageingrelated aspects in nuclear power plant operation are also examined in depth. Dr Philip G. Tipping, is a Nuclear Energy and Materials Consultant, and was formerly a Senior Materials Specialist/Metallurgist at the Swiss Federal Nuclear Safety Inspectorate (ENSI), Switzerland. He is noted for his research into ageing degradation in nuclear power plant materials and was lead author of IAEA Technical Report Series No. 448: Plant Life Management for Long Term Operation of Light Water Reactors. INDICE: Part 1 Introduction to PLiM, safety regulation and economics of nuclear power plants (NNPs): Introduction to nuclear energy, and materials and operational aspects of NNPs; Key elements and principles of nuclear power PLiM for current and longterm operation; Safety regulations for nuclear power PLiM and license renewal; Probabilistic and deterministic safety assessment methodsfor nuclear power PLiM; Assessing the socio-economic impacts of ageing and PLiM programmes for long-term operation (LTO) of NPPs. Part 2 Ageing degradationof irradiated materials in nuclear power plant systems, structures and components: mechanisms, effects and mitigation techniques: Failure prevention and analysis in nuclear power plant systems, structures and components: A holistic approach; Impact of operational loads and creep-, fatigue- and corrosion-interactions on nuclear power plant systems, structures and components; Microstructure evolution of irradiated structural materials in nuclear power plants; Stress corrosion cracking of austenitic stainless steels in high-temperature light-water reactor (LWR) environments; Void swelling and irradiation creep in LWR environments; Irradiation hardening and materials embrittlement in LWR environments; Reactor pressure vessel (RPV) annealing and mitigation in nuclear power plants. Part 3 Analysis of nuclear power plant materials, and application of advanced systems, structures and components: Characterisation techniques for assessing irradiated and ageing materials in nuclear power plant systems, structures and components; On-line and real-time corrosion monitoring techniques of metals and alloys in nuclear power plants and laboratories; Multi-scale modelling of irradiation effects in nuclear power plant materials; Development and application of instrumentation and control components in nuclear power plants; Development and application of nanostructured materials in nuclear power plants. Part 4 PLiM practices in nuclear power plants: PLiM practices for pressurised light-water nuclear reactors (PWR); PLiM practices for water-cooled water-moderated nuclear reactors (WWER); PLiM practices for boilingwater nuclear reactors (BWR): Japanese experience; PLiM practices for pressurized heavy-water nuclear reactors (PHWR); PLiM practices for sodium-cooled fast neutron spectrum nuclear reactors (SFR); PLiM practices for gas-cooled, graphitemoderated nuclear reactors (Magnox, AGR): UK experience; Outlook for nuclear power PLiM practices – summary, conclusions, recommendations.

• ISBN: 978-1-84569-511-8
• Editorial: Woodhead
• Encuadernacion: Cartoné
• Páginas: 840
• Fecha Publicación: 01/08/2010
• Nº Volúmenes: 1
• Idioma: Inglés