References
- IAEA, "Assessment and Management of Ageing of Major Nuclear Power Plant Com-ponents Important to Safety: Steam Genera-tors," Vienna, International Atomic Energy Agency nuclear energy series, ISSN 1011-4289; IAEA-TECDOC-1668, (2011).
- Nuclear Code "Kerntechnischer Ausschuss," website (www.kta-gs.de).
- IAEA, "In-Service Inspection of Nuclear Power Plants", Safety Series No. 50-P-2, IAEA Manual, 1991, pp. 3.
- Kossiakoff, A. and W.N. Sweet, "Systems Engineering: Principles and Practice," Wiley-Interscience, Hoboken, NJ, pp. 69-109, (2011).
- IAEA, "Stress corrosion cracking in light water reactors: good practices and lessons learned," Vienna, International Atomic Energy Agency nuclear energy series, ISSN 1995-7807; no. NP-T-3.13, STI/PUB/1522, PP. 5-10, (2011).
- W. S. Hazelton, W. H. Koo, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping," NUREG-0313; Rev. 2, (1988).
- R. Boudot, "Stress Corrosion Cracking of Pressurizer Nozzles in French 1300 MW(e) units," (Proceedings Fontevraud II, France, 1994) SFEN, Paris, (1994).
- EPRI-1009801, Materials Reliability Program (MRP), "Resistance to Primary Water Stress Corrosion Cracking of Alloys 690, 52, and 152 in Pressurized Water Reactors," (MRP-111), EPRI, Palo Alto, CA, USA, (2004).
- K. Smith, A. Klein, P. Saint-Paul, J. Blanchet, "Inconel 690 A material with improved corrosion resistance for PWR steam generator tubes," in: Proceedings of the Second International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, Monterey, California, September 9-12, (1985).
- ASME, "ASME Code Case N-766-Mitigation activity," (2011).
- Paul J. Kreitman, P.E., "Mitigation and repair of reactor vessel inlet/outlet nozzle using weld inlay process," Westinghouse electric company, PCI Energy service, Lake Bluff 60048, (2007).
- Mitsubishi Heavy Industries, Ltd. (MHI), "Advanced INLAY System for Reactor Vessel of PWR," E-Journal of Advanced Maintenance, Vol.4, No.3, NT49, (2009).
- S.A. Attanasio, D.S. Morton, "Measurement of the Nickel/Nickel oxide transition in Ni-Cr-Fe alloys and updated data and correlations to quantify the effect of aqueous hydrogen on primary water SCC," LM-03K049, Lockheed Martin, Schenectady, NY 12301, (2003).
- http://www.jsm.or.jp/ejam/Vol.4No.3/NT/NT49/ article.html.
- K.Dozaki. D. Akutagawa, N. Nagata, H. Takiguch, K Noring, E-jornal Adv. Maint. 2 (2010) 65-76.
- Blanchard, B.S., and W.J. Fab yrcky, "Systems Engineering and Analysis," 5th ed. Prentice-Hall International series in Industrial and Systems Engineering. Englewood Cliffs, NJ, USA: Prentice-Hall, pp. 142-161, (February 2010).
- INCOSE, "Systems Engineering Handbook," version 3.2.2., INCOSE-TP-2003-002-03.2.2., pp. 61-218, (October 2011).
- http://www.diakont.com/solutions/nuclearenergy/robotics/remote-welding-robotics/
- http://www.diakont.com/solutions/nuclearenergy/nuclear-pipe-services/rodis-crawler/.
- http://www.ocrobotics.com/
- Henry Offer; Hsueh-Wen Pao, Saratoga; William Dale Jones, Phoenix. "Method and apparatus for remotely inspection and/or for remotely inspection and/or other components used in reactor coolant systems or other process applications," Pub. No.: 2009/0307891 A1, pp. 1-2, (December 2009).