Experimental study and empirical model development for self-leveling behavior of debris bed using gas-injection
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概要
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Studies on the self-leveling behavior of debris bed are crucial in the assessment of core disruptive accident (CDA) that could occur in sodium-cooled fast reactors (SFR). To clarify the mechanisms underlying this behavior, several series of experiments were elaborately designed and conducted within a variety of conditions in recent years, under the close collaboration between Japan Atomic Energy Agency (JAEA) and Kyushu University (Japan). The current contribution, including knowledge from both experimental analyses and empirical model development, is focused on a recently developed comparatively larger-scale experimental facility using gas-injection to simulate the coolant boiling. Compared to the previous investigations, this facility can achieve a much wider range of gas velocities (presently up to a flow rate of around 300 L/min). Based on the experimental observation and quantitative data obtained, influence of various experimental parameters, including gas flow rate (～ 300 L/min), water depth (180 mm and 400 mm), bed volume (3 ～ 7 L), particle size (1 ～ 6 mm), particle density (beads of alumina, zirconia and stainless steel) along with particle shape (spherical and non-spherical) on the leveling is checked and compared. As for the empirical model development, aside from a base model which is restricted to predictions of spherical particles, the status of potential considerations on how to cover more realistic conditions (esp. debris beds formed with non-spherical particles), is also presented and discussed. This work, which gives a large palette of favorable data for a better understanding and an improved estimation of CDAs in SFRs, is expected to benefit future analyses and verifications of computer models developed in advanced fast reactor safety analysis codes.
- 一般社団法人 日本機械学会の論文
著者
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Zhang Bin
Department Of Applied Quantum Physics And Nuclear Engineering Kyushu University
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Tobita Yoshiharu
Advanced Nuclear System R&d Directorate Japan Atomic Energy Agency
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Yamano Hidemasa
Advanced Nuclear System R&d Directorate Japan Atomic Energy Agency
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Matsumoto Tatsuya
Department Of Applied Quantum Physics And Nuclear Engineering Kyushu University
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Nakamura Yuya
Department Of Aeronautics And Astronautics University Of Tokyo
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Morita Koji
Department Of Anesthesiology And Intensive Care Hamamatsu University School Of Medicine
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SUZUKI Tohru
Advanced Materials Processing Unit, National Institute for Materials Science
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TAGAMI Hirotaka
Advanced Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency
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CHENG Songbai
Advanced Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency
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TAKETA Syohei
Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University
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NISHI Sinpei
Department of Applied Quantum Physics and Nuclear Engineering, Kyushu University
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SUZUKI Tohru
Advanced Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency
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TOBITA Yoshiharu
Advanced Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency
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YAMANO Hidemasa
Advanced Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency
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Morita Koji
Department of Advanced Prosthodontics, Division of Cervico-Gnathostomatology, Programs for Applied Biomedicine, Hiroshima University Graduate School of Biomedical Sciences
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