Effect of Cladding on the Reactor Pressure Vessel Safety


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It is common for the most reactor pressure vessel (RPV) of light-water reactors used today, that the RPV made of ferrite-perlitic steel is cladded with an austenitic layer, which well resists corrosion influence. The cladding is manufactured by welding, the technology (mode of application, number of layers) is different by each manufacturer. This is the layer which comes into contact with the working media first, and is of course in cohesive contact with the RPV material. The aim of this study is to demonstrate the new approach, used for assessing the safety of the reactors today. This approach plays a decisive role in the lifespan calculation of already operating nuclear power stations, including the extension of their service period.



Materials Science Forum (Volumes 537-538)

Edited by:

J. Gyulai and P.J. Szabó




G. A. Gémes, "Effect of Cladding on the Reactor Pressure Vessel Safety", Materials Science Forum, Vols. 537-538, pp. 363-370, 2007

Online since:

February 2007




[1] Validation of neutron embrittlement for VVER 1000 & 440/312 RPVs, with emphasis on integrity assessment (TAREG 2. 01/00 Technical Report, JRC Petten, 2004), p.10.

[2] F.M. Haggag and R.K. Nanstad: Effects of Thermal Ageing and Neutron Irradiation on the Mechanical Properties of Three-Wire Stainless Steel Weld Overlay Cladding, (ORNL Report NUREG/CR-6363 and ORNL/TM-13047, 1997), p.85.

DOI: https://doi.org/10.2172/477676