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http://dx.doi.org/10.5293/KFMA.2009.12.4.054

Analysis of Local Wall Thinning around the Extraction Steam Entrance for the 6th Feedwater Heater Shell in the Nuclear Power Plants  

Song, Seok-Yoon (한국전력공사 전력연구원)
Kim, Hyung-Nam (한국전력공사 전력연구원)
Publication Information
Abstract
The feedwater heaters are Critical components in a nuclear power plant. As the operation years of heaters go by, the maintenance costs required for continuous operation increase. When the carbon steel components in nuclear make contact with running fluid, the wall thinning caused by FAC (flow accelerated corrosion) can be generated. Local wall thinning is inevitable at the area around wet steam entrance to be attacked due to the long term operation. Sometimes the shell with thinned wall is eventually ruptured. To identify the relationship between the local wall thinning and fluid behavior of the feedwater heater, the practical data of a plant, which were based on ultrasonic thickness measurement tests, were analyzed and CFD(Computed Fluid Dynamics) analyses were performed.
Keywords
Feedwater Heater; Wall Thinning; Flow Accelerated Corrosion; Ultrasonic Thickness Measurement;
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  • Reference
1 CHAM, 1994, 'An lntroduction into the Method for Irnplementing Multi-Block Grids and/or Grids with Refinements in PHOENICS,' CHAM TR/40l, Ver. 2.1
2 D. Choudhury, 1993, 'lntroduction to the Renorrnalization Group Method and Turbulence Modeling,' Fluent Inc., Technical Memorandum TM- 107
3 Electric Power Research lnstitute, 2002, 'Feedwater Heater Maintenance Guide,' p2-1-2-6
4 G. A Delp, J. D. Robison, and M T. Sedlack, 'Erosion/Corroosion in Nuclear Plant Stearn Piping: Causes and Inspection Program Guide Lines,' EPRI NP-3944
5 EPRl, 1998, 'CHECWORKSTM Application Manager,' Ver. 1.0D, TR-103198- P3, Final Report
6 KNS, 1990, '핵화학 공학' Korean Nuclear Society, V이 27, No. 5, pp. 449-457
7 G. J. Bignold and I. S. Woolsy, 'Mechanistic Aspects of Erosion/ Corrosion under Boiler Feedwater Conditions,' BIGNOLD DE WHALLEY, GARBETT and WOOLS, pp. 219-226
8 V. K. Chexal and J. S. Horowitz, 1989, 'Flow- Assisted Corrosion in Carbon Steel Piping Pararneters and Influences,' EPRI
9 NRC, 1987, 'Thinning of Pipe Walls in Nuclear Power Plants,' Bulletin 87~01
10 Song S. Y., Yoo S. Y., 2007, 'Analysis of Damage Causes for Feedwater Heater Shell Side in the Nuclear Power Plants,' Transactions of Korean Society of Pressure Vessels and Piping, Vol. 3, No. 3, pp. 18-26
11 Chexal, B., Horowitz, J., Dooly, B., Millett, P., Wood, C. and Jones, R., 1998, 'Flow- Accelerated Corrosion in Power Plant,' EPRI TR 106611- Rl