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http://dx.doi.org/10.20466/KPVP.2016.12.1.093

Development of In-Service Inspection Techniques for PGSFR  

Kim, Hoe Woong (한국원자력연구원)
Joo, Young Sang (한국원자력연구원)
Lee, Young Kyu (한국원자력연구원)
Park, Sang Jin (한국원자력연구원)
Koo, Gyeong Hoi (한국원자력연구원)
Kim, Jong Bum (한국원자력연구원)
Kim, Sung Kyun (한국원자력연구원)
Publication Information
Transactions of the Korean Society of Pressure Vessels and Piping / v.12, no.1, 2016 , pp. 93-100 More about this Journal
Abstract
Since the sodium-cooled fast reactor is operated in a hostile environment due to the use of liquid sodium as its coolant, advanced techniques for in-service inspection are required to periodically verify the integrity of the reactor. This paper presents the development of in-service inspection techniques for Proto-type Generation IV Sodium-cooled Fast Reactor. First, the 10 m long plate-type ultrasonic waveguide sensor has been developed for in-service inspection of reactor internals, and its feasibility was verified through several under-water and under-sodium experiments. Second, the combined inspection system for in-service inspection of ferromagnetic steam generator tubes has been developed. The remote field eddy current testing and magnetic flux leakage testing can be conducted simultaneously by using the developed inspection system, and the detectability was demonstrated through several damage detection experiments. Finally, the electro-magnetic acoustic transducer which can withstand high temperature and be installable in the remote operated vehicle has been developed for in-service inspection of the reactor vessel, and its detectability was investigated through damage detection experiments.
Keywords
Sodium-cooled fast reactor; In-service inspection; Reactor internals; Under-sodium viewing; Steam generator tube; Remote field eddy current testing; Magnetic flux leakage; Reactor vessel; Electro-magnetic acoustic transducer;
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