Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches3, Chapter 44. W. H. Bamford, N. a. Palm, a#39;Service experience with alloy 600 and associated Welds in Operating PWrs, ... Proceedings of the 14th environmental degradation of Materials in Nuclear Power Systems, aNS, august 23a27, 2009, virginia ... W. Bamford, J. Hall, a#39;Cracking ofalloy 600 Nozzles and Welds in PWrs: review of Cracking events and repair Service ... McIlree, a#39;Metallurgical investigation of cracking in the reactor vessel alpha loop hot leg nozzle to pipe weld at the v.
|Title||:||Nuclear Corrosion Science and Engineering|
|Publisher||:||Elsevier - 2012-02-21|