DOI QR코드

DOI QR Code

THINNED PIPE MANAGEMENT PROGRAM OF KOREAN NUCLEAR POWER PLANTS

  • Lee, S.H. (Korea Hydro & Nuclear Power Co., LTD. Central Research Institute) ;
  • Lee, Y.S. (Korea Hydro & Nuclear Power Co., LTD. Central Research Institute) ;
  • Park, S.K. (Korea Hydro & Nuclear Power Co., LTD. Central Research Institute) ;
  • Lee, J.G. (Korea Hydro & Nuclear Power Co., LTD. Central Research Institute)
  • 투고 : 2014.08.01
  • 심사 : 2015.02.23
  • 발행 : 2015.02.28

초록

Local wall thinning and integrity degradation caused by several mechanisms, such as flow accelerated corrosion (FAC), cavitation, flashing and/or liquid drop impingements, are a main concern in carbon steel piping systems of nuclear power plant in terms of safety and operability. Thinned pipe management program (TPMP) had been developed and optimized to reduce the possibility of unplanned shutdown and/or power reduction due to pipe failure caused by wall thinning in the secondary side piping system. This program also consists of several technical elements such as prediction of wear rate for each component, prioritization of components for inspection, thickness measurement, calculation of actual wear and wear rate for each component. Decision making is associated with replacement or continuous service for thinned pipe components. Establishment of long-term strategy based on diagnosis of plant condition regarding overall wall thinning is also essential part of the program. Prediction models of wall thinning caused by FAC had been established for 24 operating nuclear plants. Long term strategies to manage the thinned pipe component were prepared and applied to each unit, which was reflecting plant specific design, operation, and inspection history, so that the structural integrity of piping system can be maintained. An alternative integrity assessment criterion and a computer program for thinned piping items were developed for the first time in the world, which was directly applicable to the secondary piping system of nuclear power plant. The thinned pipe management program is applied to all domestic nuclear power plants as a standard procedure form so that it contributes to preventing an accident caused by FAC.

키워드

참고문헌

  1. B. Chexal, J. Horowitz, B. Dooly, P. Millett, C. Wood, and R. Jones, Flow Accelerated Corrosion in Power Plant, EPRI TR-106611-R2 (1998).
  2. D. Munson and J. Horowitz, Recommendations for an Effective Flow-Accelerated Corroison Program, EPRI NSAC-202L-R3 (2006).
  3. EPRI solutions, CHECWORKS Steam Feedwater Application User Guide, EPRI Product 1009600 (2004).
  4. WANO, Flow-Accelerated Corrosion, Significant Event Report 2006-1 (2006).
  5. INPO, Flow-Accelerated Corrosion, Engineering Program Guideline (2006).
  6. American Society of Mechanical Engineer, Requirement for Analytical Evaluation of Pipe Wall Thinning, ASME B&PV Sec. XI Div. 1, Code Case N-597-2 (2003).
  7. J. H. Park, K. I. Shin, C. Y. Park, and S. H. Lee, Bases of the Allowable Local Thickness of Straight Pipes in ASME Code Case N597, Trans. of the KPVP(in Korean), 2, 102 (2006).
  8. J. W. Kim, T. S. Kim, C. Y. Park, Effect of Local Wall Thinning Defect on the Collapse Moment of Elbow, Trans. of KSME (A) (in Korean), 27, 402 (2004).
  9. J. W. Kim, S. H. Lee, and C. Y. Park, Experimental evaluation of the effect of local wall thinning on the failure pressure of elbows, Nuclear Engineering and Design, 239, 2737 (2009). https://doi.org/10.1016/j.nucengdes.2009.10.003
  10. S. H. Lee, J. K. Lee, C. Y. Park and J. H. Park, Failure Test of Elbow Pipes with Local Wall Thinning under in-Plane Bending and Pressure, Proc. of World Conference on Safety of Oil and Gas Industry, p. 144 (2007).
  11. S. H. Lee, J. K Lee, and J. H. Park, Mod. Phys. Lett. B, 22, 845 (2008). https://doi.org/10.1142/S0217984908015486
  12. Y. J. Kim and C. S. Oh, Int. J. Pres. Ves. Pip., 83, 148 (2006). https://doi.org/10.1016/j.ijpvp.2005.11.001
  13. J. H. Kim, C. S. Oh, J. H. Ahn, Y. J. Kim, C. Y. Park, S. H. Lee and T. R. Kim, Finite Element Based Plastic Loads for Elbows with Local Wall Thinning, ASME Pressure Vessels and Piping Division Conference, PVP2007-26219 (2007).

피인용 문헌

  1. Thermal Stress Estimation due to Temperature Difference in the Wall Thickness for Thinned Feedwater Heater Tube vol.28, pp.3, 2015, https://doi.org/10.5855/energy.2019.28.3.001
  2. Pipe thinning model development for direct current potential drop data with machine learning approach vol.52, pp.4, 2015, https://doi.org/10.1016/j.net.2019.10.004