LES study on thermal stratification characteristics of lead-cooled fast reactor

IF 3.2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-10-04 DOI:10.1016/j.pnucene.2025.106067

Wang Yue , Liu Xuanming , Li Fengchen , Meng Shuqi , Mao Yulong , Li Qian , Cai Weihua

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Abstract

Lead-cooled fast reactor (LFR) is a fourth-generation nuclear energy system with great potential for development, but thermal delamination occurs after an emergency shutdown, which generates significant thermal stress on solid surface, thus endangering the reactor safety. In this paper, a simplified 1/6 upper plenum model is established and computational fluid dynamics software STAR-CCM+ is used to perform large-eddy simulation (LES) for the reactor shutdown, and the LES accuracy is verified based on experimental data. The results show that, in the steady-state operation condition, holes in the inner cylinder are not enough to affect the Lead-Bismuth Eutectic (LBE) flow in the upper plenum; after the shutdown, thermal stratification is gradually formed in 120 s and rises slowly with time, and the larger the outlet velocity of the reactor is, the faster the interface of thermal stratification rises, in which holes in the inner cylinder can significantly affect the LBE flow and slow down the rising rate of thermal stratification. The decrease of outlet velocity increases the non-uniformity velocity coefficient and thermal stratification number, thus affecting the formation and development of thermal stratification. It is of great significance to study the dynamic evolution of thermal stratification in the upper plenum after the reactor shutdown, so as to evaluate the reactor safety.

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铅冷快堆热分层特性的LES研究

铅冷快堆（LFR）是极具发展潜力的第四代核能系统，但在紧急停堆后会发生热分层，在固体表面产生较大的热应力，危及反应堆安全。本文建立了简化的1/6上静压室模型，利用计算流体动力学软件STAR-CCM+对反应堆停堆进行了大涡模拟（LES），并根据实验数据验证了大涡模拟的准确性。结果表明：在稳态工况下，内筒孔不足以影响上腔内铅铋共晶（LBE）流动；停堆后，热分层在120s内逐渐形成，并随时间缓慢上升，反应器出口速度越大，热分层界面上升速度越快，其中内筒孔能显著影响LBE流动，减缓热分层上升速度。出口速度的降低增加了非均匀速度系数和热分层数，从而影响热分层的形成和发展。研究反应堆停堆后上静压室热分层的动态演变，对评价反应堆安全性具有重要意义。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Progress in Nuclear Energy 工程技术-核科学技术

CiteScore

5.30

自引率

14.80%

发文量

331

审稿时长

3.5 months

期刊介绍： Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.