Investigation of flow-regime characteristics in a sloshing pool with mixed-size solid particles

Songbai Cheng; Wenhui Jin; Yitong Qin; Xiangchu Zeng; Junlang Wen

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자료유형: 학술저널

저자정보: Songbai Cheng Wenhui Jin Yitong Qin Xiangchu Zeng Junlang Wen

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제52권 제5호

발행연도: 2020.1

수록면: 925 - 936 (12page)

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To ascertain the characteristics of pool sloshing behavior that might be encountered during a coredisruptive accident of sodium-cooled fast reactors, in our earlier work several series of experiments wereconducted under various scenarios including the condition with mono-sized solid particles. It is foundthat under the particle-bed condition, three typical flow regimes (namely the bubble-impulsion dominantregime, the transitional regime and the bed-inertia dominant regime) could be identified and aflow-regime model (base model) has been even successfully established to estimate the regime transition. In this study, aimed to further understand this behavior at more realistic particle-bed conditions, aseries of simulated experiments is newly carried out using mixed-size particles. Through analyses, it isverified that for present scenario, by applying the area mean diameter, our previously-developed basemodel can provide the most appropriate predictive results among the various effective diameters. Topredict the regime transition with a form of extension scheme, a correction factor which is based on thevolume-mean diameter and the degree of convergence in particle-size distribution is suggested andvalidated. The conducted analyses in this work also indicate that under certain conditions, the potentialseparation between different particle components might exist during the sloshing process.

참고문헌 (28)

참고문헌 신청

A.M. Tentner / 2010 / Evaluation of Design Measures for Severe Accident Prevention and Consequence Mitigation

Songbai Cheng / 2018 / Investigation of fl ow regime in debris bed formation behavior with nonspherical particles / Nuclear Engineering and Technology 50(1):43~53

Y. Yamano / 2009 / Transient heat transfer characteristics between molten fuel and steel with steel boiling in the CABRI-TPA2 test / Nucl. Technol 165(2):145~165

T. G. Theofanous / 1986 / An assessment of Clinch River breeder reactor core disruptive accident energetics / Nucl. Technol 93(3):215~228

W. Maschek / 1992 / Investigations of sloshing fluid motions in pools related to recriticalities in liquid-metal fast breeder reactor core meltdown accidents / Nucl. Technol 98(1):27~43

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