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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2014.1
- 수록면
- 62 - 69 (8page)
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A huge number of carbon steel piping components installed in the secondary system of nuclear powerplants 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 thepiping components. To manage the wall thinning degradation, most of utilities in the world predict thewall thinning rate based on the computational program such as CHECWORKS, COMSY, and BRT-CICERO,evaluate the UT (Ultrasonic Test) data, and determine next inspection timing, repair or replacement, if needed.
There are several evaluation methods, such as band, blanket, and strip methods, commonly used for determiningthe wear of piping components from single UT inspection data. It has been identified that those singleUT evaluation methods not only do not consider the manufacturing features of pipes, but also may excludethe data of the most thinned point when determining the representative wear rate of piping components.
This paper describes a newly developed single UT evaluation method, E-Cross method, for solving aboveproblems and introduces application examples for several pipes and elbows. It was identified that the E-Crossmethod using the length and width of UT data excluded the most thinned points appropriate as the singleUT evaluation method for thinned piping components.
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참고문헌 (6)
참고문헌 신청
D. Poe / 2004 / CHECWORKSTM Steam/ Feedwater, Application, Guidelines for Plant Modeling and Evaluation of Component Inspection Data : 4 ~ 15
D. Poe / 2009 / CHECWORKSTM Steam/Feedwater, Application, Guidelines for Plant Modeling and Evaluation of Component Inspection Data : 4 ~ 11
D. Smith / 2010 / Mentoring Guide for Flow-Accelerated Corrosion Engineers : 7 ~ 8
J. Horowitz / 2004 / Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement Erosion, and Solid Particle Erosion in Nuclear Power Plant Piping Systems : 1 ~ 2
K. M. Hwang / 2011 / / Sci. and Technol, B 35 : 1105 ~
D. Poe / 2009 / CHECWORKSTM Steam/Feedwater, Application, Guidelines for Plant Modeling and Evaluation of Component Inspection Data : 4 ~ 11
D. Smith / 2010 / Mentoring Guide for Flow-Accelerated Corrosion Engineers : 7 ~ 8
J. Horowitz / 2004 / Recommendations for Controlling Cavitation, Flashing, Liquid Droplet Impingement Erosion, and Solid Particle Erosion in Nuclear Power Plant Piping Systems : 1 ~ 2
K. M. Hwang / 2011 / / Sci. and Technol, B 35 : 1105 ~
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