The book is divided into four parts. It begins with an overview of materials degradation due to stress corrosion, corrosion potential monitoring and passivation. Part two summarises research on susceptibility of materials to stress corrosion cracking and the ways it can be initiated. The third part of the book considers stress corrosion crack propagation processes whilst the final part includes practical case studies of corrosion in particular plants. The book reviews corrosion in a range of materials such as low alloy steels, stainless steels and nickel-based alloys.
With its distinguished editor and team of contributors, Corrosion issues in light water reactors is a standard work for the nuclear industry.
- Summarises key recent research on corrosion in light water reactors
- Includes practical case studies
An update; The effect of sulphate and chloride transients on the environmentally-assisted cracking behaviour of low-alloy RPV steels under simulated BWR conditions; Transgranular stress-corrosion cracking in austenitic stainless steels at high temperatures. Part 3 Stress corrosion cracking: Propagation: Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions
CASTOC, Part I: BWR/NWC Conditions; Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions
CASTOC, Part II: VVER Conditions; Effect of yield strength on stress corrosion crack propagation under PWR and BWR environments of hardened stainless steels; Corrosion fatigue crack growth behaviour of low-alloy RPV steels at different temperatures and loading frequencies under BWR/NWC environment; Effect of cyclic loadings on the stress corrosion crack growth rate in alloy 600 in PWR primary water; Pattern recognition model to estimate intergranular stress corrosion cracking (IGSCC) at crevices and pit sites of 304 SS in BWRs environments; Fatigue crack growth in austenitic steel AISI 304L in PWR primary water at room temperature and elevated temperature. Part 4 Practical experience: Corrosion damages of 18cr-9ni-?i steel after 25 years of operation in steam-water environments of the VK-50 reactor; Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generators; Stress corrosion cracking of a KORI 1 retired steam generator tube; A systematic study of the corrosion effects of the FRAMATOME CORD-UV technology.
Olive, J-MDr Jean-Marc Oliveis a researcher at researcher at C.N.R.S. and is Chair of the EFC Working Party 5 (Environment Sensitive Fracture).