Nuclear corrosion :  research, progress and challenges / 
edited by Stefan Ritter. 
 - 1 online resource (xxiv, 471 pages) :  illustrations 
 - European Federation of Corrosion (EFC) Series .
<br/><br/>Includes bibliographical references and index. 
<br/><br/>Front Cover -- Nuclear Corrosion: Research, Progress and Challenges -- Copyright Page -- Contents -- European Federation of Corrosion publications: Series introduction -- Volumes in the EFC series -- List of Contributors -- European Federation of Corrosion Series No. 69-Nuclear corrosion: research, progress and challenges -- Some important abbreviations -- Preface -- 1 Fifty years of nuclear corrosion in Europe: Evolutions and contributions of the working party on nuclear corrosion -- 1.1 The early days of nuclear energy 1.2 Foundation and chairmanship of the Working Party 4 on nuclear corrosion -- 1.3 Main activities of the Working Party 4 on nuclear corrosion -- 1.3.1 Working Party 4 support to EUROCORR -- 1.3.2 Working Party 4 support to the European corrosion community -- 1.3.3 Other Working Party 4 specific events -- 1.3.4 Knowledge transfer and dissemination efforts of the Working Party 4 -- 1.3.5 Working Party 4 awards -- 1.4 Summary of past, current, and future challenges -- References -- Books in the EFC series ("green books") published under the guidance of the WP 4 Other publications and special issues published under the guidance of the WP4 -- 2 Environmentally-assisted cracking of stainless steels in light water reactors -- 2.1 Introduction -- 2.2 Components made of stainless steels in boiling water reactors and pressurized water reactors -- 2.3 Welding of stainless steels -- 2.4 Stress corrosion cracking -- 2.4.1 Intergranular stress corrosion cracking in boiling water reactor environments -- 2.4.1.1 Degree of sensitization -- 2.4.1.2 Deformation -- 2.4.1.3 Environment -- 2.4.1.4 Stress -- 2.4.2 Mechanistic understanding 2.4.3 Components at risk and plant operation experience in boiling water reactor environment -- 2.4.3.1 Early intergranular stress corrosion cracking cases in sensitized Type 304 stainless steel -- 2.4.3.2 Intergranular stress corrosion cracking cases in Ti-stabilized stainless steel -- 2.4.3.3 Intergranular stress corrosion cracking cases in nonsensitized stainless steel -- 2.4.3.4 Intergranular stress corrosion cracking in pressurized water reactor environment -- 2.5 Future research needs -- Acknowledgments -- References -- 3 Mechanisms behind irradiation-assisted stress corrosion cracking 3.1 Introduction -- 3.2 Radiation effects potentially impacting irradiation-assisted stress corrosion cracking -- 3.2.1 Radiation-induced segregation at grain boundaries -- 3.2.2 Dislocation loop microstructure -- 3.2.3 Radiation-induced hardening and localized deformation -- 3.2.4 Radiation-induced precipitation -- 3.2.5 Radiation creep, swelling, and transmutation to form H and He -- 3.3 Assessment of mechanisms -- 3.3.1 Radiation-induced segregation -- 3.3.2 Radiation hardening and localized deformation -- 3.3.3 Phase stability under irradiation 
<br/><br/><label>ISBN: </label>9780128237205 0128237201 
<br/><br/><label>Nat. Bib. No.: </label>GBC094112  bnb 
<br/><br/><label>Nat. Bib. Agency Control No.: </label>019859276  Uk 
<br/><br/><label>Subjects--Topical Terms: </label><br/>Nuclear power plants--Corrosion.<br/>Corrosion and anti-corrosives.<br/>Centrales nucl�eaires--Corrosion.<br/>Corrosion and anti-corrosives<br/>Nuclear power plants--Corrosion
<br/><br/><label>LC Class. No.: </label>TK1078  / N83 2020 
<br/><br/><label>Dewey Class. No.: </label>621.4/833