Development of gas entrainment evaluation model based on distribution of pressure along vortex center line – Application to a gas entrainment experiment with traveling vortices in an open water channel flow –

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-02-01 DOI:10.1016/j.nucengdes.2024.113785
Kentaro Matsushita , Toshiki Ezure , Masaaki Tanaka , Yasutomo Imai , Tatsuya Fujisaki , Takaaki Sakai
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Abstract

Establishing an evaluation method for the gas entrainment (GE) of argon cover gas due to surface vortices is required from the perspective of safety design of sodium-cooled fast reactors (SFRs). An in-house evaluation tool for GE evaluation named StreamViewer has been developed. In previous studies, an evaluation model (original model) assuming the Burgers stretch vortex was implemented in the StreamViewer to evaluate the vortex dimple depth (gas core length). It was based on the calculation results of the pressure decrease at the vortex center point at the free surface. Since the conservativeness of the StreamViewer evaluation result with the original model has been proposed in a specific condition for a pool-type SFR, a modified evaluation model on the pressure distribution along the vortex center line (PVL model) was proposed to identify the vortex center lines as evaluation targets by connecting continuous vortex center points from the suction port to the surface using all vortex center points in an evaluation area. In the PVL model, each gas core length was evaluated based on the balance between the hydrostatic pressure and the pressure decrease distribution along the vortex center line using the three-dimensional results of computational fluid dynamics analysis. The applicability of the PVL model was confirmed by performing three-dimensional numerical analyses for the experiments where a rectangular thin plate induced unsteady traveling vortices in the open channel flow. Consequently, the GE evaluation using StreamViewer with the PVL model for the numerical analysis results could reproduce the relation between the inlet flow velocity and the gas core length, in other words, the elongation behavior of the gas core length with increased inlet velocity, in the unsteady vortex flow experiments.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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