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Analysis of Pipe Wall-thinning Caused by Water Chemistry Change in Secondary System of Nuclear Power Plant

원전 2차계통의 수화학 변화가 배관감육에 미치는 영향 분석

  • Received : 2015.11.03
  • Accepted : 2015.12.14
  • Published : 2015.12.31

Abstract

Pipe wall-thinning by flow-accelerated corrosion (FAC) is a significant and costly damage of secondary system piping in nuclear power plants (NPPs). All NPPs have their management programs to ensure pipe integrity from wall-thinning. This study analyzed the pipe wall-thinning caused by changing the amine, which is used for adjusting the water chemistry in the secondary system of NPPs. The pH change was analyzed according to the addition of amine. Then, the wear rate calculated in two different amines was compared at the steam cycle in NPPs. As a result, increasing the pH at operating temperature (Hot pH) can reduce the rate of FAC damage significantly. Wall-thinning is affected by amine characteristics depending on temperature and quality of water.

Keywords

References

  1. EPRI, TR-106611-R1, Flow-Accelerated Corrosion in Power Plant (1998).
  2. EPRI, TR-1011231, Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement, and Solid Particle Erosion in Nuclear Power Plant Piping Systems (2004).
  3. EPRI, TR-1022295, Mentoring Guide for Flow-Accelerated Corrosion Engineers (2010).
  4. EPRI, Technical Report 2001000563, Recommendations for an Effective Flow-Accelerated Corrosion Program (NSAC-202L-R4) (2013).
  5. E. H. Lee, K. M. Kim, H. P. Kim, Corros. Sci. Tech., 12, 280 (2013). https://doi.org/10.14773/cst.2013.12.6.280
  6. EPRI, TR-102952-R2, PWR Advanced Amine Application Guidelines (1997).
  7. Danienl C. Harris, Quantitative Chemical Analysis, 8th Edition (2012).
  8. EPRI, TR-1018102, CHECWORKS Steam Feedwater Application (SFA) Version 3.0 User Guide (2008).
  9. EPRI, TR-1009599, Guidelines for Plant Modeling and Evaluation of Component Inspection Data (2004).

Cited by

  1. Analysis of Wall-Thinning Effects Caused by Power Uprates in the Secondary System of a Nuclear Power Plant vol.15, pp.3, 2016, https://doi.org/10.14773/cst.2016.15.3.135