The thermal stress and pressure stress caused by mixing of cold and hot water on a tee junction of piping system in reactor cooling systems of nuclear power plants are the potential place to crack pipe. These stresses are generated due to temperature distribution unevenly in regions where hot and cold flows are intensively mixed together. As operating plants become older and life time extension activities are initiated, operators need screening criteria to exclude risks of pipe cracking. The Kuosheng boiling water reactor (BWR) units 1 and 2, owned by Taiwan Power Company (TPC), started commercial operations in 1981 and 1983, respectively. The purpose of this paper is to assess the Von Mises stresses and deformation of tee piping in Kuosheng’s RHR system by the Fluid Solid Interaction (FSI) simulation. Furthermore, the simulation result compare with the experiment result during the fourth refueling outage per decade in 2014. The temperature and the stress of monitor points established by experiment are all located in the range between maximum and minimum of the experiment result.
Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant
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Huang, P, & Li, C. "Fluid Solid Interaction (FSI) Simulation of a Tee Piping in Operating Nuclear Power Plant." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A002. ASME. https://doi.org/10.1115/ICONE25-66022
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