Corrosion mechanisms and their consequences for nuclear power Plants

• Autorzy: Berg H.-P.
• Języki publikacji: EN

Abstrakty

EN

It is well known that operational conditions in light water reactors strongly influence the corrosion processes. This paper gives an overview which types of corrosion are identified in operating practice based on the evaluation of events which are reported to the authorities in line with the German reporting criteria. It has been found that the main contributor is the stress corrosion cracking. Several examples of different corrosion mechanisms and their consequences are provided for PWR although a high standard of quality of structures, systems and components has been achieved. Recommendations have been given to check the plant specifications concerning the use of auxiliary materials or fluids during maintenance as well as to examine visually the outer surfaces of austenitic piping with regard to residua of adhesive or adhesive tapes within the framework of in-service inspections. However, events in the last two years shows that such problems cannot be totally avoided.

Słowa kluczowe

EN

corrosion; corrosion types; operating experience; nuclear power plants

• Wydawca: Polskie Towarzystwo Bezpieczeństwa i Niezawodności
• Czasopismo: Journal of Polish Safety and Reliability Association
• Rocznik: 2009
• Tom: Vol. 1
• Strony: 23--32
• Opis fizyczny: Bibliogr. 11 poz., fot., rys., tab., wykr.

Twórcy

autor

Berg H.-P.

• Bundesamt für Strahlenschutz (BfS), Salzgitter, Germany

Bibliografia

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• [2] Electric Power Research Institute (2009). EPRI Portfolio 2009-41.01-1, Primary Systems Corrosion Research, 2009 Nuclear Research Areas.
• [3] Fukuya, K. et al. (2008). Effects of dissolved hydrogen and strain rate on IASCC behavior in highly irradiated stainless steels. Journal of Nuclear Science and Technology 45, 452-458.
• [4] Gersinska, R. (2003). Aktueller Kenntnisstand der Schadensbildungen durch interkristalline Spannungsrisskorrosion in austenitischen Rohrleitungen. BfS-SK-IB-01, BfS Salzgitter, Februar 2003 (in German).
• [5] Havel, R. (2003). IAEA Extrabudgetary programme on mitigation of intergranular stress corrosion cracking in RBMK reactors.
• [6] Jiao, Z. & Was, G. S. (2008). Localized deformation and IASCC initiation in austenitic stainless steels. Journal of Nuclear Materials 382, 203-209.
• [7] Kerntechnischer Ausschuss. (1996). KTA 3201.2. Components of the Reactor Coolant Pressure Boundary of Light Water Reactors;Part 2: Design and Analysis.
• [8] Kerntechnischer Ausschuss. (1999). KTA 3210.4, Components of the Reactor Coolant Pressure Boundary of Light Water Reactors; Part 4: Inservice Inspections and Operational Monitoring.
• [9] Michel, F., Reck, H. & Schulz, H. (2001). Experience with piping in German NPPs with respect to ageing-related aspect. Nuclear Engineering and Design 207, 307-316.
• [10] Schlicht-Szesny. (2001). Korrosionsvorgänge und Korrosionsschäden in kerntechnischen Anlagen. BfS-KT-IB-87, BfS Salzgitter, Dezember 2001 (in German).
• [11] Schulz, H. (2001). Limitations of the inspection and testing concepts for pressurised components from the viewpoint of operating experience. EUROSAFE 2001. Nuclear Installation Safety, Seminar I, 51-69.