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http://dx.doi.org/10.1016/j.net.2018.09.016

An experimental study on pool sloshing behavior with solid particles  

Cheng, Songbai (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-Sen University)
Li, Shuo (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-Sen University)
Li, Kejia (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-Sen University)
Zhang, Ting (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-Sen University)
Publication Information
Nuclear Engineering and Technology / v.51, no.1, 2019 , pp. 73-83 More about this Journal
Abstract
It is important to clarify the mechanisms of molten-fuel-pool sloshing behavior that might be encountered during a core disruptive accident of sodium-cooled fast reactors. In this study, motivated by acquiring some evidence for understanding the characteristics of this behavior at more realistic conditions, a number of experiments are newly performed by injecting nitrogen gas into a water pool with the accumulation of solid particles. To achieve comprehensive understanding, various parameters including particle bed height, particle size, density, shape, gas pressure along with the gas-injection duration, were employed. It is found that due to the different interaction mechanisms between solid particles and the gas bubble injected, three kinds of regimes, termed respectively as the bubble-impulsion dominant regime, the transitional regime and the bed-inertia dominant regime, could be identified. The performed analyses also suggest that under present conditions, all our experimental parameters employed can have noticeable impact on the regime transition and resultant sloshing intensity (e.g. maximum elevation of water level at pool peripheries). Knowledge and fundamental data from this work will be used for the future verifications of fast reactor severe accident codes in China.
Keywords
Sodium-cooled fast reactor; Core disruptive accident; Molten fuel pool; Sloshing behavior; Solid particles;
Citations & Related Records
Times Cited By KSCI : 2  (Citation Analysis)
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1 H. Yamano, T. Suzuki, Y. Tobita, T. Matsumoto, K. Morita, Validation of the SIMMER-IV severe accident computer code on three-dimensional sloshing behavior, in: Proc. The Eighth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), Beppu, Japan, 2012. Dec. 9-12, 2012.
2 K. Morita, T. Matsumoto, Y. Emura, et al., Investigation on sloshing response of liquid in a 2D pool against hydraulic disturbance, in: The Ninth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), Buyeo, Korea, November, vols. 16-19, 2014, 2014.
3 S. Cheng, S. Li, K. Li, N. Zhang, T. Zhang, A two-dimensional experimental investigation on the sloshing behavior in a water pool, Ann. Nucl. Energy 114 (2018) 66-73.   DOI
4 H. Yamano, S. Fujita, Y. Tobita, K. Kamiyama, S. Kondo, K. Morita, E.A. Fischer, D.J. Brear, N. Shirakawa, X. Cao, M. Sugaya, M. Mizuno, S. Hosono, T. Kondo, W. Maschek, E. Kiefhaber, G. Buckel, A. Rineiski, M. Flad, T. Suzuki, P. Coste, S. Pigny, J. Louvet, T. Cadiou, SIMMER-iii: a Computer Program for LMFR Core Disruptive Accident Analysis, Version 3.a Model Summary and Program Description, Japan Nuclear Cycle Development Institute, Ibaraki, Japan, 2003. JNC-TN-9400-2003-071.
5 P. Liu, S. Yasunaka, T. Matsumoto, K. Morita, K. Fukuda, Y. Tobita, Simulation of the dynamic behavior of the solid particle bed in a liquid pool: sensitivity of the particle jamming and particle viscosity models, J. Nucl. Sci. Technol. 43 (2) (2006) 140-149.   DOI
6 P. Liu, S. Yasunaka, T. Matsumoto, K. Morita, K. Fukuda, H. Yamano, Y. Tobita, Dynamic behavior of a solid particle bed in a liquid pool: SIMMER-III code verification, Nucl. Eng. Des. 237 (2007) 527-535.
7 S. Cheng, S. Wang, G. Jiang, J. Yu, Y. Qian, P. Gong, J. Cui, Development and analysis of a regime map for predicting debris bed formation behavior, Ann. Nucl. Energy 109 (2017) 658-666.   DOI
8 S. Cheng, H. Yamano, T. Suzuki, Y. Tobita, Y. Nakamura, B. Zhang, T. Matsumoto, K. Morita, Characteristics of self-leveling behavior of debris beds in a series of experiments, Nucl. Eng. Technol. 45 (3) (2013) 323-334.   DOI
9 S. Cheng, P. Gong, S. Wang, J. Cui, Y. Qian, T. Zhang, G. Jiang, Investigation of flow regime in debris bed formation behavior with non-spherical particles, Nuclear Engineering and Technology 50 (1) (2018) 43-53.   DOI
10 L.S. Fan, C. Zhu, Principles of Gas-Solid Flows, Cambridge University Press, UK, 1998.
11 T. Suzuki, K. Kamiyama, H. Yamano, S. Kubo, Y. Tobita, R. Nakai, K. Koyama, A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention, J. Nucl. Sci. Technol. 51 (4) (2014) 493-513.   DOI
12 T.G. Theofanous, C.R. Bell, An assessment of Clinch River breeder reactor core disruptive accident energetics, Nucl. Technol. 93 (3) (1986) 215-228.
13 W. Maschek, C. Munz, L. Meyer, Investigations of sloshing fluid motions in pools related to recriticalities in liquid-metal fast breeder reactor core meltdown accidents, Nucl. Technol. 98 (1) (1992) 27-43.   DOI
14 H. Yamano, Y. Onoda, Y. Tobita, Transient heat transfer characteristics between molten fuel and steel with steel boiling in the CABRI-TPA2 test, Nucl. Technol. 165 (2) (2009) 145-165.   DOI
15 S. Cheng, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita, An experimental study on local fuelecoolant interactions by delivering water into a simulated molten fuel pool, Nucl. Eng. Des. 275 (2014) 133-141.   DOI
16 S. Cheng, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita, A numerical study on local fuelecoolant interactions in a simulated molten fuel pool using the SIMMER-III code, Ann. Nucl. Energy 85 (11) (2015) 740-752.   DOI