Researching | Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies

NUCLEAR TECHNIQUES, Volume. 47, Issue 7, 070603(2024)

Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies

Yan WANG, Jiaming LU, Jiaye YAO, Gang HONG^*, and Yaoli ZHANG

Author Affiliations

College of Energy, Xiamen University, Xiamen 361005, China

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References(16)

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[4] Liu X J, Yang D M, Yang Y et al. Computational fluid dynamics and subchannel analysis of lead-bismuth eutectic-cooled fuel assembly under various blockage conditions[J]. Applied Thermal Engineering, 164, 114419(2020).

[5] Liu J T, Peng T J, Wang G et al. Sub-channel analysis of lead-bismuth fast reactor fuel assembly with wire spacers for China initiative accelerator driven system[J]. Annals of Nuclear Energy, 170, 108965(2022).

[6] Lodi F, Grasso G. Extension of the sub-channel code ANTEO+ to the mixed convection regime[J]. Nuclear Engineering and Design, 322, 368-378(2017).

[8] Bubelis E, Schikorr M. Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlations[J]. Nuclear Engineering and Design, 238, 3299-3320(2008).

[9] Cheng S K, Todreas N E. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles—bundle friction factors, subchannel friction factors and mixing parameters[J]. Nuclear Engineering and Design, 92, 227-251(1986).

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[11] CONG Tenglong, WANG Junjie, XIAO Yao et al. Analysis of transverse flow characteristics in LBE-cooled wire-wrapped fuel assembly[J]. Atomic Energy Science and Technology, 56, 2725-2734(2022).

[12] WANG Jingjie. Study on flow and heat transfer mechanism of liquid lead-bismuth alloy in wire-wound fuel rod assembly[D](2021).

[13] LIU Shuyong, YU Dali, MEI Huaping et al. Turbulent-Prandtl-number models for liquid lead-bismuth in triangular rod bundles[J]. Nuclear Techniques, 45, 030604(2022).

[14] Ali M Y, Wu G W, Liu S Y et al. Research of coupled wall conduction effects on forced and natural circulation of LBE in CLEAR-S[J]. Progress in Nuclear Energy, 111, 74-84(2019).

[15] YAO Jun, ZHANG Xisi, HU Wenjun et al. Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident[J]. Nuclear Techniques, 41, 020604(2018).

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[17] JIN Shuang, LIU Xiaojing, CHENG Xu. Optimization method of CFD coarse grid numerical simulation based on neural network[J]. Nuclear Techniques, 44, 060601(2021).

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Yan WANG, Jiaming LU, Jiaye YAO, Gang HONG, Yaoli ZHANG. Optimization of subchannel analysis for lead-bismuth reactor fuel assemblies[J]. NUCLEAR TECHNIQUES, 2024, 47(7): 070603

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Paper Information

Category: Research Articles

Received: Dec. 19, 2023

Accepted: --

Published Online: Aug. 27, 2024

The Author Email: HONG Gang (洪钢)

DOI:10.11889/j.0253-3219.2024.hjs.47.070603

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