Numerical study on the thermal hydraulic effect of flow blockage in liquid metal cooled reactor core rod bundles

IF 3.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Progress in Nuclear Energy Pub Date : 2025-03-18 DOI:10.1016/j.pnucene.2025.105743

Lingping Song , Jiahao Zhao , Shiqi Wang , Bin Han , Xiaoliang Zhu , Bao-Wen Yang , Aiguo Liu , Shenghui Liu , Junlin Huang

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引用次数: 0

Abstract

Liquid metal reactor has become one of the most promising types of Gen IV nuclear energy systems due to its excellent safety and thermal hydraulic characteristics. Flow blockage is a severe thermal accident especially in liquid metal reactors compared to other reactors. When fuel assembly is blocked, decrease of coolant will cause the temperature to dramatically rise in the cladding and unexpected flow downstream the blocks. The safety of the reactor will be affected. In this paper, a lead-cooled 7 pin bare rod bundle model was established based on CFD to simulate the flow behaviors under blockage accidents. Cases with different geometries including block shape, axial length, block area and boundary conditions were set to investigate the effect of flow blockage. The temperature, pressure and velocity field downstream the blocks were obtained. It was found that the boundary conditions and geometry parameters have coupled effect on the flow performance of the blockage. A critical axial length of blocks was found to make the effect of blockage reach the peak. The research provides a fundamental basis for the design and safe operation of liquid metal reactor.

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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.