Abstract
Maintenance, as discussed in this chapter, is important to ensure the structural integrity and reliability of the plant over its life span by compensating for any uncertainties that require attention when a new reactor is designed. Maintenance is also important for the implementation of improvements to the plant design through operational experience. This chapter first introduces the general thinking behind the maintenance of nuclear power plants (NPPs) and then explains the maintenance typical of fast reactors (FRs) that is characterized by high-temperature low-pressure conditions due to the use of sodium and its respective reactions with air and water. Finally, this chapter discusses the specifics of FR maintenance, operation, inspection, and repair.
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Further Readings
K. Miya, G. Yagawa, in Reactor Structural Engineering. Series in Nuclear Engineering, (University of Tokyo Press, 1977) (in Japanese)
Y. Ando, K. Okabayashi, in Genshiryoku Puranto no Kozo Sekkei (Structural Engineering in Nuclear Plants). Series in Nuclear Engineering Vol. 3, (University of Tokyo Press, 1977) (in Japanese)
S. Ishino, in Shosha Sonsho (Irradiation Damage). Series in Nuclear Engineering Vol. 8, (University of Tokyo Press, 1979) (in Japanese)
F. Masuyama, K. Maruyama (translation), in Evaluation of Damage Mechanism and Lifetime of Elevated Temperature Components, (Nikkan Kogyo Shimbun, Ltd., 1993) (in Japanese)
Penny, Marriott, in Design for Creep, 2nd edn. (Chapman & Hall 1995)
References
Kazuyuki Demachi, the Author and Editor, Nuclear Power Text Book, in Nuclear Maintenance Engineering, (Ohmsha, Ltd., 2010) (in Japanese)
S. Nakai, Y. Kaneko, K. Mukai, Restart of prototype FR Monju after long-term shut-down. J. Jpn. Soc. Maint 9(4) (2011) in Japanese
Japan Electric Association, Code for maintenance at nuclear power plants. JEAC 4209, (2007) (in Japanese)
Japan Electric Association, Guide for maintenance at nuclear power plants. JEAG 4210, (2007) (in Japanese)
Atomic Energy Society of Japan (AESJ) standards, Code on implementation and review of nuclear power plant ageing management programs 2008 (AESJ-SC- P005: 2008) (in Japanese)
Japan Society of Mechanical Engineering (JSME), Codes for power generation facilities rules on fitness-for-services for nuclear power plants. (JSME S NA1) (in Japanese)
S. Nakai, M. Uchihashi, Y. Kaneko, Maintenance of prototype FBR Monju. Jpn. Soc. Maint. 8th Annual Conference, October, (2011) (in Japanese)
IAEA, in “Safety of Nuclear Power Plants”: Design Specific Safety Requirements、 SSR-2/1, (International Atomic Energy Agency, Vienna, 2012)
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Nakai, S. (2017). Maintenance. In: Kasahara, N. (eds) Fast Reactor System Design. An Advanced Course in Nuclear Engineering, vol 8. Springer, Singapore. https://doi.org/10.1007/978-981-10-2821-2_9
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DOI: https://doi.org/10.1007/978-981-10-2821-2_9
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