Corrosion Issues in Light Water Reactors: Stress Corrosion Cracking: Volume 51 (European Federation of Corrosion (EFC) Series) [Hardcover] [Jun 22, 2007] Féron, D and Olive, J-M

Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications. 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 Content: Front matter , Pages i-iii Copyright , Page iv Contributor contact details , Pages xiii-xviii European Federation of Corrosion (EFC) publications: Series introduction , Pages xix-xx Volumes in the EFC series , Pages xxi-xxv Preface , Pages xxvii-xxviii , Damien Féron, Jean-Marc Olive 1 - An overview of materials degradation by stress corrosion in PWRs , Pages 3-24 , P.M. Scott 2 - Corrosion potential monitoring in nuclear power environments , Pages 25-43 , A. Molander 3 - Kinetics of passivation of a nickel-base alloy in high temperature water , Pages 44-56 , A. Machet, A. Galtayries, P. Marcus, P. Jolivet, M. Foucault, P. Combrade, P. Scott 4 - IASCC susceptibility under BWR conditions of welded 304 and 347 stainless steels , Pages 59-69 , M.L. Castaño, B. Van Der Schaaf, A. Roth, C. Ohms, D. Gavillet, S. Van Dyck 5 - The effect of lead on resistance of low alloy steel to SCC in high temperature water environments , Pages 70-75 , K. Matocha, G. Rožnovská, V. Hanus 6 - Effect of cold work hardening on stress corrosion cracking of stainless steels in primary water of pressurized water reactors , Pages 76-86 , O. Raquet, E. Herms, F. Vaillant, T. Couvant, J.M. Boursier 7 - Effect of strain-path on stress corrosion cracking of AISI 304L stainless steel in PWR primary environment at 360 °C , Pages 87-102 , T. Couvant, F. Vaillant, J.M. Boursier, D. Delafosse 8 - Dynamic strain ageing of deformed nitrogen-alloyed AISI 316 stainless steels , Pages 103-118 , U. Ehrnstén, A. Toivonen, M. Ivanchenko, V. Nevdacha, Y. Yagozinskyy, H. Hänninen 9 - Laboratory results of stress corrosion cracking of steam generator tubes in a ‘complex’ environment – an update , Pages 119-129 , O. Horner, E.-M. Pavageau, F. Vaillant, O. de Bouvier 10 - The effect of sulphate and chloride transients on the environmentally-assisted cracking behaviour of low-alloy RPV steels under simulated BWR conditions , Pages 130-148 , S. Ritter, H.P. Seifert 11 - Transgranular stress-corrosion cracking in austenitic stainless steels at high temperatures , Pages 149-161 , A. Brozova, S. Lynch 12 - Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 1: BWR/NWC Conditions , Pages 165-185 , S. Ritter, H.P. Seifert, B. Devrient, A. Roth, U. Ehrnstén, M. Ernestová, M. Žamboch, J. Föhl, T. Weissenberg, D. Goméz-Briceño, J. Lapeña 13 - Crack growth behaviour of low-alloy steels for pressure boundary components under transient light water reactor operating conditions – CASTOC, Part 2: VVER conditions , Pages 186-199 , M. Ernestová, M. Žamboch, B. Devrient, A. Roth, U. Ehrnstén, J. Föhl, T. Weissenberg, D. Gomézbriceño, J. Lapeña, S. Ritter, H.P. Seifert 14 - Effect of yield strength on stress corrosion crack propagation under PWR and BWR environments of hardened stainless steels , Pages 200-210 , M.L. Castaño, M.S. García, G. de Diego, D. Goméz-Briceño 15 - Corrosion fatigue crack growth behaviour of low-alloy RPV steels at different temperatures and loading frequencies under BWR/NWC environment , Pages 211-230 , S. Ritter, H.P. Seifert 16 - Effect of cyclic loadings on the stress corrosion crack growth rate in alloy 600 in PWR primary water , Pages 231-244 , C. Guerre, O. Raquet, L. Duisabeau, G. Turluer 17 - Pattern recognition model to estimate intergranular stress corrosion cracking (IGSCC) at crevices and pit sites of 304 SS in BWRs environments , Pages 245-259 , M. Urquidi-MacDonald 18 - Fatigue crack growth in austenitic steel AISI 304L in PWR primary water at room and elevated temperature , Pages 260-269 , I. Nedbal, J. Kunz, J. Siegl 19 - Corrosion damage to 18Cr-9Ni-Ti steel after 25 years of operation in steam-water environments of the VK-50 reactor , Pages 273-288 , G.V. Filyakin, V.K. Shamardin, Yu.D. Goncharenko, V.A. Kazakov 20 - Comprehensive investigation of the corrosion state of the heat exchanger tubes of steam generators , Pages 289-305 , K. Varga, Z. Németh, A. Szabó, K. Radó, D. Oravetz, K.É. Makó, Z. Homonnay, E. Kuzmann, S. Stichleutner, P. Tilky, J. Schunk, G. Patek 21 - Stress corrosion cracking of a Kori 1 retired steam generator tube , Pages 306-315 , H.P. Kim, S.S. Hwang, D.J. Kim, J.S. Kim, Y.S. Lim, M.K. Joung 22 - A systematic study of the corrosion effects of the FRAMATOME CORD-UV technology , Pages 316-327 , K. Radó, K. Varga, Z. Németh, I. Varga, J. Somlai, D. Oravetz, K.É. Makó, Z. Homonnay, E. Kuzmann, J. Borszéki, P. Halmos, P. Tilky, J. Schunk Index , Pages 328-340 Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). The nuclear industry needs to be able to predict the service life of these power plants and develop appropriate maintenance and repair practices to ensure safe long term operation. This important book sums up key recent research on corrosion in light water reactors and its practical applications.

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

Stress corrosion cracking is a major problem in light water nuclear reactors, whether pressurised water reactors (PWRs) or boiling water reactors (BWRs). This important book summarises up key research on corrosion in light water reactors and its practical applications.