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http://dx.doi.org/10.1016/j.net.2021.08.024

Knowledge from recent investigations on sloshing motion in a liquid pool with solid particles for severe accident analyses of sodium-cooled fast reactor  

Xu, Ruicong (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-sen University Tang-Jia Wan)
Cheng, Songbai (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-sen University Tang-Jia Wan)
Li, Shuo (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-sen University Tang-Jia Wan)
Cheng, Hui (Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-sen University Tang-Jia Wan)
Publication Information
Nuclear Engineering and Technology / v.54, no.2, 2022 , pp. 589-600 More about this Journal
Abstract
Investigations on the molten-pool sloshing behavior are of essential value for improving nuclear safety evaluation of Core Disruptive Accidents (CDA) that would be possibly encountered for Sodium-cooled Fast Reactors (SFR). This paper is aimed at synthesizing the knowledge from our recent studies on molten-pool sloshing behavior with solid particles conducted at the Sun Yat-sen University. To better visualize and clarify the mechanism and characteristics of sloshing induced by local Fuel-Coolant Interaction (FCI), experiments were performed with various parameters by injecting nitrogen gas into a 2-dimensional liquid pool with accumulated solid particles. It was confirmed that under different particle-bed conditions, three representative flow regimes (i.e. the bubble-impulsion dominant, transitional and bed-inertia dominant regimes) are identifiable. Aimed at predicting the regime transitions during sloshing process, a predictive empirical model along with a regime map was proposed on the basis of experiments using single-sized spherical solid particles, and then was extended for covering more complex particle conditions (e.g. non-spherical, mixed-sized and mixed-density spherical particle conditions). To obtain more comprehensive understandings and verify the applicability and reliability of the predictive model under more realistic conditions (e.g. large-scale 3-dimensional condition), further experimental and modeling studies are also being prepared under other more complicated actual conditions.
Keywords
Sodium-cooled fast reactor; Nuclear safety; Core disruptive accident; Molten-pool sloshing motion; Solid particles;
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Times Cited By KSCI : 4  (Citation Analysis)
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1 S. Cheng, S. Li, K. Li, T. Zhang, An experimental study on pool sloshing behavior with solid particles, Nucl. Eng. Technol. 51 (1) (2019) 73-83.   DOI
2 Z. Li, N. Kobayashi, A. Nishimura, M. Hasatani, A method to predict the minimum fluidization velocity of binary mixtures based on particle packing properties, Chem. Eng. Commun. 192 (7) (2005) 918-932.   DOI
3 C.E. Agu, C. Pfeifer, B.M.E. Moldestad, Prediction of void fraction and minimum fluidization velocity of a binary mixture of particles: bed material and fuel particles, Powder Technol. 349 (2019) 99-107.   DOI
4 S. Cheng, X. Li, F. Liang, S. Li, K. Li, Study on sloshing motion in a liquid pool with non-spherical particles, Prog. Nucl. Energy 117 (2019) 103086.   DOI
5 B. Raj, P. Chellapandi, P.V. Rao, Sodium Fast Reactors with Closed Fuel Cycle, CRC Press, Boca Raton, USA, 2015.
6 S. Cheng, P. Gong, S. Wang, J. Cui, Y. Qian, T. Zhang, G. Jiang, Investigation of flow regime in debris bed formation behavior with nonspherical particles, Nucl. Eng. Technol. 50 (1) (2018) 43-53.   DOI
7 A. Bachrata, F. Bertrand, N. Marie, F. Serre, A comparative study on severe accident phenomena related to melt progression in SFR and PWR, J. Nucl. Eng. Radiat. Sci. 7 (3) (2021), 030801.   DOI
8 R. Xu, S. Cheng, Review of the molten-pool sloshing motion in case of Core Disruptive Accident: experimental and modeling studies, Prog. Nucl. Energy 133 (2021) 103647.   DOI
9 S. Cheng, H. Tagami, H. Yamano, T. Suzuki, Y. Tobita, B. Zhang, T. Matsumoto, K. Morita, Evaluation of debris bed self-leveling behavior: a simple empirical approach and its validations, Ann. Nucl. Energy 63 (2014) 188-198.   DOI
10 L.H.S. Phan, P. Ngo, F. Matsuoka, R. Miura, T. Matsumoto, K. Morita, Experimental study on self-leveling behavior of binary-mixed particles in cylindrical bed using gas-injection method, in: 12th International Topical Meeting on Reactor Thermal-Hydraulics, Operation, and Safety (NUTHOS-12), Qingdao, China, 2018, pp. 14-18. Oct.
11 S. Cheng, W. Jin, Y. Qin, X. Zeng, J. Wen, Investigation of flow-regime characteristics in a sloshing pool with mixed-sized solid particles, Nucl. Eng. Technol. 52 (5) (2019) 925-936.   DOI
12 H. Yamano, S. Fujita, Y. Tobita, K. Kamiyama, M.K. Kondo Sa, E. Fischer, D. Brear, N. Shirakawa, X. Cao, M. Sugaya, Simmer-III: A Computer Program for LMFR Core Disruptive Accident Analysis Version 3 A Model Summary and Program Description, Japan Nuclear Cycle Devlopment Institute, 2003. JNC-TN-9400-2003-071.
13 K. Morita, T. Matsumoto, Y. Emura, T. Abe, I. Tatewaki, H. Endo, 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 (NTHAS-9), Buyeo, Korea, 2014, pp. 16-19. Nov.
14 H. Yamano, Y. Onoda, Y. Tobita, I. Sato, 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 T. Suzuki, Y. Tobita, K. Kawada, H. Tagami, J. Sogabe, K. Matsuba, K. Ito, H. Ohshima, A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor, Nucl. Eng. Technol. 47 (3) (2015) 240-252.   DOI
16 S. Cheng, T. Zhang, C. Meng, T. Zhu, Y. Chen, Y. Dong, X. Chen, Y. Ye, A comparative study on local fuel-coolant interactions in a liquid pool with different interaction modes, Ann. Nucl. Energy 132 (2019) 258-270.   DOI
17 D. Geldart, Estimation of basic particle properties for use in fluid-particle process calculations, Powder Technol. 60 (1) (1990) 1-13.   DOI
18 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
19 B. Zhang, T. Harada, D. Hirahara, T. Matsumoto, K. Morita, K. Fukuda, H. Yamano, T. Suzuki, Y. Tobita, Experimental investigation on self-leveling behavior in debris beds, Nucl. Eng. Des. 241 (1) (2011) 366-377.   DOI
20 D. Geldart, Gas Fluidization Technology, John Wiley & Sons, Chichester, 1986.
21 L.H.S. Phan, P.M. Ngo, R. Miura, Y. Tasaki, T. Matsumoto, W. Liu, K. Morita, Self-leveling behavior of mixed solid particles in cylindrical bed using gas-injection method, J. Nucl. Sci. Technol. 56 (1) (2019) 111-122.   DOI
22 S. Chiba, T. Chiba, A.W. Nienow, H. Kobayashi, The minimum fluidisation velocity, bed expansion and pressure-drop profile of binary particle mixtures, Powder Technol. 22 (2) (1979) 255-269.   DOI
23 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
24 A. Tentner, E. Parma, T. Wei, R. Wigeland, Severe Accident Approach-Final Report. Evaluation of Design Measures for Severe Accident Prevention and Consequence Mitigation, Argonne National Laboratory, 2010. ANL-GENIV-128.
25 S. Cheng, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita, A numerical study on local fuel-coolant interactions in a simulated molten fuel pool using the SIMMER-III code, Ann. Nucl. Energy 85 (2015) 740-752.   DOI
26 W. Maschek, C.-D. 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
27 T. Zhang, S. Cheng, T. Zhu, C. Meng, X.a. Li, A new experimental investigation on local fuel-coolant interaction in a molten pool, Ann. Nucl. Energy 120 (2018) 593-603.   DOI
28 S. Cheng, K. Matsuba, M. Isozaki, K. Kamiyama, T. Suzuki, Y. Tobita, An experimental study on local fuel-coolant interactions by delivering water into a simulated molten fuel pool, Nucl. Eng. Des. 275 (2014) 133-141.   DOI
29 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
30 S. Cheng, S. Li, K. Li, T. Zhang, N. Zhang, X.a. Li, F. Liang, Prediction of flow-regime characteristics in pool sloshing behavior with solid particles, Ann. Nucl. Energy 121 (2018) 11-21.   DOI
31 S. Cheng, R. Xu, W. Jin, Y. Qin, X. Zeng, S. Li, K. Li, Experimental study on sloshing characteristics in a pool with stratified liquids, Ann. Nucl. Energy 138 (2020) 107184.   DOI
32 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 (5) (2007) 524-535.   DOI
33 L.S. Fan, C. Zhu, Principles of Gas-Solid Flows, Cambridge University Press, Cambridge, UK, 2005.
34 S. Cheng, H. Yamano, T. Suzuki, Y. Tobita, Y. Nakamura, B. Zhang, T. Matsumoto, K. Morita, Empirical correlations for predicting the self-leveling behavior of debris bed, Nucl. Sci. Tech. 24 (1) (2013), 010602.
35 S. Cheng, D. Hirahara, Y. Tanaka, Y. Gondai, B. Zhang, T. Matsumoto, K. Morita, K. Fukuda, H. Yamano, T. Suzuki, Experimental investigation of bubbling in particle beds with high solid holdup, Exp. Therm. Fluid Sci. 35 (2) (2011) 405-415.   DOI
36 S. Cheng, H. Tagami, H. Yamano, T. Suzuki, Y. Tobita, Y. Nakamura, S. Taketa, S. Nishi, B. Zhang, T. Matsumoto, K. Morita, Experimental study and empirical model development for self-leveling behavior of debris bed using gas-injection, Mech. Eng. J. 1 (4) (2014). TEP0022-TEP0022.   DOI
37 T. Theofanous, C. Bell, An assessment of Clinch River Breeder Reactor core disruptive accident energetics, Nucl. Sci. Eng. 93 (3) (1986) 215-228.   DOI
38 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: The 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-8), Beppu, Japan, 2012, pp. 9-12. Dec.