Main Article Content
Piping systems in nuclear power plants (NPPs) and their safety class classification acc. to IAEA Safety Standards and requirements of ASME and RCC-M codes are shortly presented.
Creative Commons CC BY 4.0
ASME Boiler and Pressure Vessel Code, Section III: Rules for construction of nuclear facility components, American Society of Mechanical Engineers, New York, 2015.
AFCEN RCC-M: Design and Construction Rules for Mechanical Components of PWR Nuclear Islands, 2012 Edition.
Classification of systems, structures and components of a nuclear facility, Guide YVL B.2, STUK, 15 November 2013.
Safety classi cation of structures, systems and components in nuclear power plants, IAEA Safety Standards Series No. SSG-30, IAEA, Vienna, 2014.
Safety of Nuclear Power Plants: Design, IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), IAEA, Vienna, 2016.
Safety Assessment for Facilities and Activities, IAEA Safety Standards Series No. GSR Part 4 (Rev. 1), IAEA, Vienna, 2016.
N. Kajiyama, K. Hamamura, K. Murayama: Hitachis Involvement in Nuclear Power Plant Construction in Japan, Hitachi Review, vol. 58, 2009, No. 2.  Finland: Olkiluoto 3 Gradually Taking Shape, Nuclear News Letter, AREVA NP Customer Information, November 2007.
J. McIntyre: Hinkley Point C...full steam ahead!, Nuclear Exchange, vol. 10, May 2013, pp. 31-34.
Ph. Malouines, G. Bezdikian: From the Safety Approach of a Nuclear Power Plant, to the Manufacturing and Welding of Mechanical Components in Line with RCC-M Code, Seminarium: Kody, normy i przepisy dotyczące projektowania, wytwarzania oraz systemów zarządzania jakością obowią- zujących w przemyśle jądrowym, MG/IS/UDT, Warszawa, 22-24.09.2015.
P. Gaio: AP1000: The PWR Revisited, IAEA International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century, 27 October 2009.
The ABWR Plant. General Descripcion, GE Energy, USA, December 2006.