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주증기계통 오리피스 후단 소구경 배관의 감육 및 누설 발생

Cause Analysis for the Wall Thinning and Leakage of a Small Bore Piping Downstream of an Orifice

  • 투고 : 2013.10.25
  • 심사 : 2013.10.28
  • 발행 : 2013.10.31

초록

A number of components installed in the secondary system of nuclear power plants are exposed to aging mechanisms such as FAC (Flow-Accelerated Corrosion), Cavitation, Flashing, and LDIE (Liquid Droplet Impingement Erosion). Those aging mechanisms can lead to thinning of the components. In April 2013, one (1) inch small bore piping branched from the main steam line experienced leakage resulting from wall thinning in a 1,000 MWe Korean PWR nuclear power plant. During the normal operation, extracted steam from the main steam line goes to condenser through the small bore piping. The leak occurred in the downstream of an orifice. A control valve with vertical flow path was placed on in front of the orifice. This paper deals with UT (Ultrasonic Test) thickness data, SEM images, and numerical simulation results in order to analyze the extent of damage and the cause of leakage in the small bore piping. As a result, it is concluded that the main cause of the small bore pipe wall thinning is liquid droplet impingement erosion. Moreover, it is observed that the leak occurred at the reattachment point of the vortex flow in the downstream side of the orifice.

키워드

참고문헌

  1. Jeffrey Horowitz, Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement Erosion, and Solid Particle Erosion in Nuclear Power Plant Piping Systems, EPRI 1011231, Final Report, November (2004).
  2. K. M. Hwang, Investigation on the Evaluation for Liquid Droplet Impingement Erosion through Prediction Model and Experiment, JMST, B (Korean), 35, 1105 (2011).
  3. Y. S. Lee, S. G. Park, and J. S. Lim, Extraction Steam Line Drain Failure, KHNP-FAC-2009-EPRI-01, Rev. 0 (2009).
  4. C. Crowe, M. Sommerfield, and Y. Tsuji, Multiphase Flows with Droplets and Particles, CRC Press (1998).
  5. K. M. Hwang and D. Y. Lee, A Study on the Thermal Hydraulic Analysis and B-Scan Inspection for LDIE Degradation of Carbon Steel Piping in a Nuclear Plant, Corros. Sci. Tech., 11, 218 (2012). https://doi.org/10.14773/cst.2012.11.6.218
  6. R. Morita and Y. Cchiyama, Development of a Wall Thinning Rate Model for Liquid Droplet Impingement Erosion, ASME, PVP2012-78443 (2012).
  7. J. H. Brunton and M. C. Rochester, Erosion of Solid Surfaces by the Impact of Liquid Drops, Erosion-Treatise on Materials Science and Technology, 16, edited by C. M. Preece, Academic Press, New York (1979).

피인용 문헌

  1. Cause Analysis of Flow Accelerated Corrosion and Erosion-Corrosion Cases in Korea Nuclear Power Plants vol.15, pp.4, 2016, https://doi.org/10.14773/cst.2016.15.4.182
  2. 원주 방향 두께가 불균일한 배관의 진동 모드 특성을 이용한 배관 감육 검사 기법 연구 vol.21, pp.1, 2013, https://doi.org/10.7842/kigas.2017.21.1.18
  3. Development of ToSPACE for Pipe Wall Thinning Management in Nuclear Power Plants vol.9, pp.1, 2013, https://doi.org/10.4236/wjnst.2019.91001
  4. Thermal Stress Estimation due to Temperature Difference in the Wall Thickness for Thinned Feedwater Heater Tube vol.28, pp.3, 2013, https://doi.org/10.5855/energy.2019.28.3.001