铅铋冷却快堆堵流事故下堵块参数对流动传热的影响

doi:10.11889/j.0253-3219.2018.hjs.41.020604

Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (2): 20604-020604.doi: 10.11889/j.0253-3219.2018.hjs.41.020604

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles Next Articles

Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident

YAO Jun¹, ZHANG Xisi², HU Wenjun², CHAI Xiang¹, YANG Yanhua¹

1. Shanghai Jiao Tong University, Shanghai 200240, China;
2. China Institute of Atomic Energy, Beijing 102413, China

Received:2017-11-01 Revised:2017-12-20 Online:2018-02-10 Published:2018-02-06

Abstract

Abstract: [Background] Lead-cooled fast reactor (LFR) is one of six candidates for Generation IV nuclear systems. Although lead-bismuth eutectic (LBE) has excellent neutron properties, thermal-hydraulic performance and inherent safety features, the structure and cladding materials could be eroded by LBE coolant. The erosion products could accumulate in fuel assembly and grow as a blockage influencing the heat transfer of cladding and coolant. [Purpose] This study aims to investigate the block parameter effect on thermal-hydraulic performance of single fuel assembly in lead-bismuth subcritical reactor under various blockage accidents. [Methods] Based on actual geometry and material properties, modeling of single fuel assembly was established. Five blockage accidents were numerically simulated by the commercial computational fluid dynamics (CFD) software STAR-CCM+ with different block parameters. [Results] Temperature variations along the axial direction of cladding inner face and subchannel center were obtained and compared. Axial velocity distributions around block were analyzed. Influence of block parameters for the coolant backflow and the property of flow fields were achieved. [Conclusion] The maximum temperature rise unanimously occurs inside block. Different block parameters diversely influence flow and heat transfer.

Key words: LFR, Blockage accident, Block parameter, CFD

CLC Number:

TL364.4

YAO Jun, ZHANG Xisi, HU Wenjun, CHAI Xiang, YANG Yanhua. Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident [J].Nuclear Techniques, 2018, 41(2): 20604-020604.

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Effect of block parameter on fluid flow and heat transfer in LBE-cooled fast reactor under blockage accident

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