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Numerical simulations of upper plenum thermal-hydraulics of Monju reactor vessel using high resolution mesh models

詳細メッシュモデルを用いた「もんじゅ」原子炉上部プレナムの熱流動解析評価

大平 博昭; 本多 慶; 素都 益武

Ohira, Hiroaki; Honda, Kei; Sotsu, Masutake

In order to evaluate the upper plenum thermal-hydraulics of the Monju reactor vessel, we have performed detail calculations under the 40% rated power operational condition using high resolution mesh models by a commercial FVM code, FrontFlow/Red. In this study, we applied a high resolution meshes around the flow holes (FHs) on the inner barrel. We mainly made clear that the thermal-hydraulics did not change largely since the flow rates through the FHs were small enough to the total coolant flow rate but were affected largely in case without FHs on the honeycomb structure.

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