In-situ eddy current monitoring of structural components in nuclear power plants

抄録

This paper discusses the feasibility of Eddy Current Monitoring (ECM) system as a in-situ evaluation method of crack propagation in a Boiling Water Reactor (BWR) environment. For the purpose, we review an ECM experiment conducted at a System Safety Benchmark Facility (SSBF) with a large-scale austenitic stainless steel pipe specimen. Several slits were prepared at the Heat Affected Zones (HAZs) and weld lines from the inner surface. After exerting the load, Eddy Current Testing (ECT) probes attached on the outer surface of the specimen provide the crack propagation signal. Numerical simulation of eddy current signals based on the experimental conditions indicate that this system is capable of monitoring the crack growth in BWR environments.