Researching | Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor

Journals >NUCLEAR TECHNIQUES >Volume 46 >Issue 11 >Page 110602 > Article

NUCLEAR TECHNIQUES
Vol. 46, Issue 11, 110602 (2023)

Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor

Qi CHEN, Yufan LING, Pengcheng ZHAO^*, Yanan ZHAO, and Tao YU

Author Affiliations

School of Nuclear Science and Technology, University of South China, Hengyang 421001, China

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DOI: 10.11889/j.0253-3219.2023.hjs.46.110602 Cite this Article

Qi CHEN, Yufan LING, Pengcheng ZHAO, Yanan ZHAO, Tao YU. Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(11): 110602 Copy Citation Text

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References

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[11] GONG Hao. Analysis of blockage accident for single assembly of LBE-cooled fast reactor[D](2014).

[12] 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).

[13] CHEN Baowen, DENG Jian, LING Yufan et al. Analysis of blockage accident of lead-based fast reactor single-box fuel assembly based on CFD[J]. Nuclear Power Engineering, 42, 277-281(2021).

[14] SUN Chang, JIAO Shouhua, CHAI Xiang et al. Thermal hydraulic analysis of LBE-cooled rod bundle based on CFD method[J]. Atomic Energy Science and Technology, 54, 1386-1394(2020).

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[16] DING Li, LUO Beibei, HUA Xiao et al. Research on prevention and detection technology of flow channel blockage accident of plate-type fuel elements[J]. Nuclear Techniques, 43, 040002(2020).

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[18] Guo Y, Wang G, Qian D et al. Accident safety analysis of flow blockage in an assembly in the JRR-3M research reactor using system code RELAP5 and CFD code FLUENT[J]. Annals of Nuclear Energy, 122, 125-136(2018).

[19] YANG Yong. Design and implement of a CFD pre/post process software based on SolidWorks[D](2008).

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Qi CHEN, Yufan LING, Pengcheng ZHAO, Yanan ZHAO, Tao YU. Analysis of typical flow blockage accidents of single annular fuel assembly for lead-bismuth cooled fast reactor[J]. NUCLEAR TECHNIQUES, 2023, 46(11): 110602

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