Description
This publication provides readers in industry and academia with a comprehensive review of the development and understanding of zirconium within the context of it use in nuclear reactors. It presents input from leading experts in the relevant fields and encompasses the full spectrum of zirconium as a metal, its properties and use. It is unique in the breadth of its scope. The publication’s coverage includes: alloy development in the nuclear industry and guidelines on commercial alloys and alloys under development; extraction and consolidation of zirconium, from ore to ingot to component; deformation and texture of various alloys with analysis of the effects of irradiation damage on physical and mechanical behaviour as well as deformation and creep during irradiation and damage due to oxidation and corrosion; and ductility and fractures of alloys.
Keywords
Metallurgy, Zirconium, Properties, Classification, Ductility, Zirconium Alloys, Practical Experience, Current Understanding, Phenomena, Application, Industry, Pressurized Water Reactors, PWRs, Comprehensive Review, Metal, Use, Alloy Development, Nuclear Industry, Guidelines, Commercial Alloys, Extraction, Consolidation of Zirconium, Ore, Ingot, Component, Deformation, Texture, Analysis, Irradiation Damage, Physical and Mechanical Behaviour, Deformation, Thermal Creep, Irradiation Creep, Oxidation, Corrosion Performance, Fractures, Fabrication of Zirconium, Technological Consequences, Remedies of Dimensional Changes, Neutron Irradiation, Alloying Elements, Fuel Cladding, Boiling Water Reactor, BWR, Light Water Reactor, LWR, Pressurized Heavy Water Reactor, PHWR, Internal Friction, Anelasticity, History of Models, Delayed Hydride Cracking, DHC
