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One of the strategies of cost reduction of nuclear power generation is increase of power outputs. In order to achieve increase of power outputs of a Boiling Water Reactor (BWR), it is extremely important to evaluate coolant flow in a lower plenum of a BWR. Although the simulation by a CFD code is helpful to predict the coolant flow in a lower plenum, experimental data to verify the simulation results are not enough, and the simulation results considerably depends on models. Hence, the present study is focusing on the establishment of the benchmark of CFD code by using the visualization method in a lower plenum. The objective of the present study is to clarify the flow structure of a lower plenum in detail, and to investigate effects of complicated flow structure of lower plenum on core inlet flow. We constructed a 1/10 model of a lower plenum to measure velocity profiles with LDV and PIV. And differential pressure of the lower plenum was measured with differential pressure instrument. In the experiment, it turned out that flow structure of the lower plenum vary depending on experimental condition.

Effects of Lower Plenum Flow Structure on Core Inlet Flow of ABWR