[2B17-18] Design of Reactor Equipment

[2B17] Structural Integrity Assessment of the Advanced Reactor Internals under Flow-Induced Loads for the Further Enhancement of Safety of a PWR Plant

*Hirokazu Sugiura¹, Shigeyuki Watanabe¹, Akihisa Iwasaki¹, Hideyuki Morita¹, Koji Maeta¹, Keisuke Matsuyama¹, Daisuke Kanamori² (1. Mitsubishi Heavy Industries, Ltd., 2. Kansai Electric Power co., Inc.)

Keywords:nuclear power plant, reactor internals, structural integrity, flow-induced vibration

For the further enhancement of safety of a PWR plant, new type reactor internals in which a large number of the Rod Cluster Control Assembly can be installed were developed. To verify the structural integrity of the advanced reactor internals under flow-induced loads, scale-model testing and analyses were performed.