• Satoru NakaiEmail author
Part of the An Advanced Course in Nuclear Engineering book series (ACNE, volume 8)


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.


Nuclear Power Plant Stress Corrosion Crack Maintenance Activity Maintenance Program Maintenance Method 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

Further Readings

  1. K. Miya, G. Yagawa, in Reactor Structural Engineering. Series in Nuclear Engineering, (University of Tokyo Press, 1977) (in Japanese)Google Scholar
  2. 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)Google Scholar
  3. S. Ishino, in Shosha Sonsho (Irradiation Damage). Series in Nuclear Engineering Vol. 8, (University of Tokyo Press, 1979) (in Japanese)Google Scholar
  4. F. Masuyama, K. Maruyama (translation), in Evaluation of Damage Mechanism and Lifetime of Elevated Temperature Components, (Nikkan Kogyo Shimbun, Ltd., 1993) (in Japanese)Google Scholar
  5. Penny, Marriott, in Design for Creep, 2nd edn. (Chapman & Hall 1995)Google Scholar


  1. 1.
    Kazuyuki Demachi, the Author and Editor, Nuclear Power Text Book, in Nuclear Maintenance Engineering, (Ohmsha, Ltd., 2010) (in Japanese)Google Scholar
  2. 2.
    S. Nakai, Y. Kaneko, K. Mukai, Restart of prototype FR Monju after long-term shut-down. J. Jpn. Soc. Maint 9(4) (2011) in JapaneseGoogle Scholar
  3. 3.
    Japan Electric Association, Code for maintenance at nuclear power plants. JEAC 4209, (2007) (in Japanese)Google Scholar
  4. 4.
    Japan Electric Association, Guide for maintenance at nuclear power plants. JEAG 4210, (2007) (in Japanese)Google Scholar
  5. 5.
    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)Google Scholar
  6. 6.
    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)Google Scholar
  7. 7.
    S. Nakai, M. Uchihashi, Y. Kaneko, Maintenance of prototype FBR Monju. Jpn. Soc. Maint. 8th Annual Conference, October, (2011) (in Japanese)Google Scholar
  8. 8.
    IAEA, in “Safety of Nuclear Power Plants”: Design Specific Safety Requirements、 SSR-2/1, (International Atomic Energy Agency, Vienna, 2012)Google Scholar

Copyright information

© Springer Nature Singapore Pte Ltd. 2017

Authors and Affiliations

  1. 1.Japan Atomic Energy AgencyIbarakiJapan

Personalised recommendations