참고문헌
- USNRC, 1987, "Thinning of Pipe Walls in Nuclear Power Plants", U.S. Nuclear Regulatory Commission, Washington, DC, Bulletic 87-01.
- USNRC, 1989, "Erosion Corrosion Induced Pipe Wall Thinning", U.S. Nuclear Regulatory Commission, Washington, DC, Generic Letter 89-08.
- Choi, Y. H., and Kang, S. C., 2000, "Evaluation of Piping Integrity in Thinned Main Feedwater Pipes", Journal of the Korean Nuclear Society, Vol. 32, No. 2, pp. 67-76.
- Lee, E. H., Kim, K. M., Kim, H. P. and Kim, D. J., 2015, "Effect of Cr on Flow Accelerated Corrosion of Carbon Steel", Corrosion Science and Technology, Vol. 14, No. 1, pp. 25-32. doi: http://dx.doi.org/10.14773/cst.2015.14.1.25
- Lee, G. G., Lee, E. H., Kim, S. W. and Kim, D. J., 2016, "Development of Statistical Modeling Methodology for Flow Accelerated Corrosion: Effect of Flow Rate, Water Temperature, pH, and Cr Content", Trans. of the KPVP, Vol. 12, No. 2, pp. 40-49. doi: http://dx.doi.org/10.20466/KPVP.2016.12.2.040
- EPRI, 2011, SGMP : Investigation of Steam Generator Secondary-Side Degradation, Electric Power Research Institute, Palo Alto, CA, TR-1022830.
- Lee, S. H. and Lee, Y. S., 2015, "Study on Cause and Effect of SG Feed Water Ring Through-Wall Hole," Trans. of the KPVP, Vol. 11, No. 1, pp. 61-68.
- Reg. Guide 1.61 Rev1, 2007, "Damping Values for Seismic Design of Nuclear Power Plants", U.S. Nuclear Regulatory Commission, Washington, DC.
- Reg. Guide 1.92 Rev1, 1976, "Combining Modal Responses and Spatial Components in Seismic Response Analysis", U.S. Nuclear Regulatory Commission, Washington, DC.
- ASME BPVC Sec III, 1977, "Rules for Construction of Nuclear Facility Components," American Society of Mechanical Engineers, NY.