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[en] The reactor pressure vessel head (RPVH) is an integral part of the reactor coolant pressure boundary. Its integrity is important for the safe and reliable operation of the nuclear power plants (NPP). After detection of the leakage and cracks on the RPVH in a French NPP, followed by another that occurred in a NPP in the USA, methods and frequency of inspections were defined, and are strictly regulated by the US NRC Order EA-03-009 (substituted lately by ASME Code Case N791-1) since 2003. INETEC’s ARCHER system is designed to provide full scope inspection of the RPVH, by using various test modules and by performing the surface repair action on J-groove weld. It is adjustable to work with different types of penetration nozzles and thermal sleeves on both VVER and PWR types of NPPs. The paper describes the system’s capabilities and features, and its advantages compared to other systems for performing the RPVH inspection and repair activities on PWR and VVER reactors.