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).

• 1. Fifty years of nuclear corrosion in Europe: evolutions and contributions of the EFC Working Party on Nuclear Corrosion2. Environmentally-assisted cracking of stainless steels in light water reactors3. Mechanisms behind irradiation-assisted stress corrosion cracking4. Environmentally-assisted cracking of nickel-base alloys in light water reactors5. Environmentally-assisted cracking of carbon and low-alloy steels in light water reactors6. Flow-accelerated corrosion in nuclear power plants7. Understanding the corrosion processes of fuel cladding in pressurised water reactors8. Corrosion behaviour of stainless steels in nitric acid in the context of nuclear fuel reprocessing plants9. The corrosion behaviour of stainless steel in conditions relevant to the storage of intermediate level radioactive waste10. The corrosion of radioactive waste disposal canisters based on in-situ tests11. Copper behaviour in geological nuclear waste disposal12. Material research for the supercritical water-cooled reactor - summary and open issues13. Corrosion of structural materials by liquid metals used in fusion, fission and spallation