Light water reactors in Japan are expected to restart sequentially after given permission in condition to meet the new regulatory requirements. Since several safety related systems were added to the plants through the process of the new regulatory requirements, the numbers of components to be inspected, which is already a large amount, will increase even more after the restart in Japan. Effective measure will be required to command maintenance activities by reasonably assigning limited resource. The authors have planned a research project aiming optimization of maintenance considering influence of fluid leakage behavior with pipe failure, mainly targeting less-safety related piping and components. The experimental facility which has the ability to evaluate the fluid leakage behavior with pipe failure was constructed. By using this facility, it is able to conduct the test of the water jet, the flashing and the steam flow leaked from various flaw geometries of the piping.

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