참고문헌 (26)

1. Cubicciotti D, J Nuc Mater, 152 (1988) 259. 

2. Villien B, Zheng Y, Lister D H, Proceedings of the Twenty Sixth Annual CNS-CNA Student Conference. Toronto (June 2001). 

3. Smith C L, Shah V N, Kao T, Apostolakis G, NUREG/CR-5632: Incorporating aging effects into probabilistic risk assessment - A feasibility study utilizing reliability physics models, US Nuclear Regulatory Commission (2001). 

4. 10.1016/S0308-0161(99)00087-3 Dooley R B and Chexal V K, International J Pressure Vessel Piping, 77 (2000) 85. 

   상세보기

5. Moon J Ho, Chung H Ho, Sung Ki W, Kim Uh Ch, and Pho Jae S, Nuclear Engg and Technology, 37 (2005) 375. 

6. Shoji T, Lu Z, Takeda Y and Sato Y, Towards proactive materials degradation management in NPP - Today and future, CD proceedings of the 14th Asia Pacific Corrosion Control Conference (APCCC), October 21-24, 2006, Shanghai, China (2006). 

7. 10.1016/j.jnucmat.2008.08.024 Kain V, Roychowdhury S, Mathew T, Bhandakkar A, Journal of Nuclear Materials, 383 (2008) 86. 

   상세보기

8. 10.1016/j.engfailanal.2011.06.007 Kain V, Roychowdhury S, Ahmedabai P, Barua D K, Engg Failure Analysis 18 (2011) 2081. 

   상세보기

9. 10.1016/j.jnucmat.2012.05.045 Singh J L, Kumar Umesh, Kumawat N, Kumar Sunil, Kain Vivekanand, Anantharaman S and Sinha A K, J Nucl Mater, 429 (2012) 226. 

   상세보기

10. 10.5006/1.3278426 Satoh T, Shao Y, Cook W G, Lister D H and Uchida S, Corrosion, 63 (2007) 770. 

    상세보기

11. ASM Handbook, Vol. 13A, Corrosion - Fundamentals, testing and protection, ASM International, The Materials Information Society, Materials Park, Ohio (2003). 

12. Kain V, Prasad G E and Gadiyar H S, Indian Journal of Technology, 30 (1992) 341. 

13. Watanabe Yutaka, Sue Kiwamu, Abe Hiroshi, “Effects of Cr Content and Environmental Factors on FAC Rate of Carbon Steels”, Proceedings of 2009 ASME Pressure Vessel and Piping Division Conference, July 26-30, (2009), Prague, Czech Republic, (CD-ROM), PVP2009-78126. 

14. 10.1016/0045-8732(85)90079-8 Jonas O, Power, 129(3) (1985) 102. 

    상세보기

15. Bignold G J, Garbett K, Garnsey R and Woolsey I S, Erosion corrosion of nuclear steam generators, Water chemistry of nuclear reactor systems 2, British Nuclear Energy Society BNES, 1 (1981)5. 

16. 10.1016/0029-5493(92)90084-9 Remy F N and Bouchacourt M, Nuclear Engineering and design, 133 (1992) 23. 

    상세보기

17. ASTM A 335 (06), Standard specification for seamless ferritic alloy - steel pipe for high temperature service, ASTM, Philadelphia, USA (2006). 

18. 10.1016/j.jnucmat.2008.08.030 Tapping R L, Journal of Nuclear Materials, 383 (2008) 1. 

    상세보기

19. BARC internal report issued by Post Irradiation Examination Division - Preliminary report on failure examination of feeder pipe B-12 (s) of RAPS-2, 2007. 

20. 10.1016/j.jnucmat.2005.03.021 Koike M H, J Nucl Mater, 342 (2005) 125. 

    상세보기

21. Uchida S et al., Evaluation methods for flow accelerated corrosion and liquid droplet impingement in nuclear power plants, Second international conference on Flow Accelerated Corrosion (FAC 2010), Lyon, France, 2010. 

22. Dooley R B, Power Plant Chemistry, 10(2) (2008) 68. 

23. BARC report issued by Materials Science Division - Metallurgical analyses of the HP Turbine exhaust pipe of RAPS #2 - issued to NPCIL, 2008. 

24. BARC report issued by Materials Science Division - Metallurgical analyses of the FAC affected secondary components for KGS2 - issued to NPCIL, 2008. 

25. BARC report issued by Materials Science Division - Metallurgical analyses of the 65NB 45？ elbow and straight pipe sections from the feed water system of TAPS-4 - issued to NPCIL, 2009. 

26. BARC report issued by Materials Science Division - Metallurgical analyses of the extraction line and stage 2 drain of turbine at KAPS #2 - issued to NPCIL, 2009.