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

NUCLEAR TECHNIQUES, Volume. 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

show less

Abstract Get PDF(in Chinese)

Figures&Tables (19)

References (21)

Paper Information

References(21)

[1] ZENG Fulin, TANG Mao, ZHAO Pengcheng et al. Influence of the pitch-to-diameter ratio on the circumferential non-uniformity of annular fuel outer temperature distribution[J]. Nuclear Techniques, 46, 090601(2023).

[2] CHEN Zhao, XIAO Yingjie, ZHAO Pengcheng et al. Research on effective temperature calculation method of annular fuel cell[J]. Nuclear Techniques, 45, 120603(2022).

[3] Hejzlar P, Kazimi M S. Annular fuel for high-power-density pressurized water reactors: motivation and overview[J]. Nuclear Technology, 160, 2-15(2007).

[4] WEI Shiying, WANG Chenglong, TIAN Wenxi et al. Research progress in key thermal-hydraulic issue of lead-based fast reactor[J]. Atomic Energy Science and Technology, 53, 326-336(2019).

[5] Zhang J. A review of steel corrosion by liquid lead and lead-bismuth[J]. Corrosion Science, 51, 1207-1227(2009).

[6] XU Mi[M]. Fast reactor safety analysis(2011).

[7] ZHAO Pengcheng, LIU Zijing, YU Tao. Transient analysis on unprotected partial flow blockage of hottest fuel assembly for a small natural circulation lead-cooled fast reactor[J]. Nuclear Power Engineering, 40, 23-27(2019).

[8] Shi K L, Li S Z, Zhang X L et al. Partial flow blockage analysis of the hottest fuel assembly in SNCLFR-100 reactor core[J]. Nuclear Science and Techniques, 29, 16(2018).

[9] Luo X, Cao L K, Feng W P et al. Development of a subchannel code for blockage accidents of LMFRs based on the 3D fuel rod model[J]. Nuclear Science and Techniques, 33, 27(2022).

[10] Liu P, Chen X N, Rineiski A et al. Transient analyses of the 400 MWth-class EFIT accelerator driven transmuter with the multi-physics code: SIMMER-III[J]. Nuclear Engineering and Design, 240, 3481-3494(2010).

[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).

[15] Xia H, Wu Y, Tian W et al. Development of thermal hydraulic analysis code of annular fuel under flow blockage condition[J]. Annals of Nuclear Energy, 151, 107962(2021).

[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).

[17] Wang Y J, Wang M J, Ju H T et al. CFD simulation of flow and heat transfer characteristics in a 5×5 fuel rod bundles with spacer grids of advanced PWR[J]. Nuclear Engineering and Technology, 52, 1386-1395(2020).

[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).

[20] WEI Junhan, ZHAO Minfu. Numerical simulation study on the flow of annular fuel rod bundle coolant[C], 1311-1321(2019).

[21] YANG Yun. Numerical simulation and analysis on flow blockage accident of fuel subassembly for sodium cooled fast reactor[D](2019).

Tools

Get Citation

Copy Citation Text

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

Download Citation

EndNote(RIS)BibTex Plain Text

Set citation alerts for article

Save article for my favorites

Paper Information

Category: Research Articles

Received: Jun. 18, 2022

Accepted: --

Published Online: Dec. 23, 2023

The Author Email:

DOI:10.11889/j.0253-3219.2023.hjs.46.110602

Topics

laser devices and laser physics

Lasers and Laser Optics

laser manufacturing

Instrumentation, Measurement and Metrology