In 2017 the EFC's Working Party (WP) on Nuclear Corrosion marked its 50th anniversary with a workshop comprising invited talks from renowned experts covering almost the entire range of nuclear corrosion topics. As a result of these workshop contributions, Nuclear Corrosion: Research, Progress and Challenges is being published as part of the "Green Book series of the EFC. This book will build upon the foundations of the very first book published in this series in 1989 ("Number 1 - Corrosion in the nuclear industry). Since that publication, this WP has guided and supported the research and application of results in the broad field of nuclear corrosion.
This newest volume consists of an overview of the state-of-the-art of research in some of the most important areas of nuclear corrosion. The chapters covered include ageing phenomena in light water reactors, reprocessing plants, as well as in nuclear waste disposal, supercritical water and liquid metal systems. This book will be a vital resource for both researchers and engineers working within the nuclear field in both academic and industrial environments.
- Discusses industry related aspects of materials in nuclear power generation and how these materials deal with the environment
- Provides comprehensive coverage of the topic, written by noted experts in the field
- Includes coverage of nuclear waste corrosion
1. Fifty years of nuclear corrosion: from a pioneer period to a mature industry and science 2. Environmentally-assisted cracking of stainless steels in light water reactors 3. Mechanisms behind irradiation-assisted stress corrosion cracking 4. Environmentally-assisted cracking of nickel-base alloys in light water reactors 5. Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors 6. Flow-accelerated corrosion in nuclear power plants 7. Understanding the corrosion processes of fuel cladding 8. Corrosion behaviour of stainless steels in nitric acid in the context of nuclear fuel reprocessing plants 9. The corrosion behaviour of stainless steel in conditions relevant to the storage of intermediate level radioactive waste 10. The corrosion of radioactive waste disposal canisters based on in-situ tests 11. Copper behaviour in geological nuclear waste disposal 12. Material research for the supercritical water-cooled reactor
summary and open issues 13. Corrosion of structural materials by liquid metals used in fusion, fission and spallation
Stefan Ritter (Dipl.-Ing., Material Science and Engineering, Friedrich-Alexander University Erlangen-Nürnberg, Germany) did his masters/diploma at Siemens Power Generation (KWU) in Erlangen (Germany) and performed research on stress corrosion cracking of austenitic stainless steels at Framatome ANP in Erlangen thereafter. Since 2001 he has been employed by the Paul Scherrer Institute (Nuclear Energy and Safety Research Division, Laboratory for Nuclear Materials) as a research scientist in the field of plant ageing management. He is currently working on different national and international research projects related to EAC of light water reactor structural materials and to mitigation technologies (e.g., noble metal chemical addition/NobleChem or Zn addition) and is also involved in consulting for EPRI. In 2004 he was one of the founding members of the ECG-COMON (European Cooperative Group on Corrosion Monitoring of Nuclear Materials, www.ecg-comon.org) and is currently Webmaster of this group. In 2012 he became the Scientific Secretary of the ICG-EAC (International Cooperative Group on Environmentally-Assisted Cracking of Water Reactor Materials, www.icg-eac.org) and in 2016 he was elected as Chairman of the Nuclear Corrosion Working Party of the European Federation of Corrosion (EFC).