This study was performed to clarify the effects of flaw detection probability on piping reliability of a nuclear power plant. Stress-corrosion cracking (SCC) is still sporadically detected in austenitic stainless steel piping in Japanese BWR plants. The suitability for continued service of cracked pipes is basically evaluated by using the “Rules on fitness -for service for nuclear power plants.” Here future inspection rules are employed. However, the possibility of undetection of existing cracks and that of inaccurate measurements cannot be eliminated in UT-based inspection. Thus a probabilistic fracture mechanics (PFM) analysis was carried out referring measured flaw size, and the reliability of piping was evaluated considering the possibility of undetection of existing cracks and that of inaccurate measurements. The results of the analysis indicate that, if the interval and quality of the inspection are maintained at a certain specified level, the possibility of undetection of existing cracks and that of inaccurate measurements less affect failure probability.
Reliability Assessment of Piping in a Nuclear Power Plant Considering Flaw Detection Probability
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Machida, H, Yamashita, N, Yoshimura, S, & Yagawa, G. "Reliability Assessment of Piping in a Nuclear Power Plant Considering Flaw Detection Probability." Proceedings of the ASME/JSME 2004 Pressure Vessels and Piping Conference. Pressure Vessel and Piping Codes and Standards. San Diego, California, USA. July 25–29, 2004. pp. 247-254. ASME. https://doi.org/10.1115/PVP2004-2698
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