A review of research on liquid-metal-cooled reactor and supercritical carbon dioxide Brayton cycle coupled system

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

Progress in Nuclear Energy Pub Date : 2025-08-06 DOI:10.1016/j.pnucene.2025.105957

Zhengyu Gong , Yaolei Zou , Songbai Cheng , Bing Tan , Pengcheng Zhao

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引用次数: 0

Abstract

The supercritical carbon dioxide (S-CO₂) Brayton cycle is an advanced energy conversion system with many advantages including high power conversion efficiency, system compactness and high flexibility. The coupling of Liquid Metal-cooled Reactor (LMR) with the S-CO₂ Brayton cycle represents a promising direction in the development of nuclear energy systems, fully leveraging the strengths of both technologies. However, the coupled system is in the preliminary design stage. This paper carries out an integrated review of research activities about the coupled systems, with a focus on coupled system design, the Liquid Metal (LM)-S-CO₂ coupled heat transfer experiment and numerical simulation, and the LM-S-CO₂ Heat eXchanger Tube Rupture (HXTR) accident. This review summarizes the achievements and shortcomings of the existing studies, which can provide a valuable reference for the future research in this domain.

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液态金属冷却堆与超临界二氧化碳布雷顿循环耦合系统的研究进展

超临界二氧化碳（S-CO2）布雷顿循环是一种先进的能量转换系统，具有功率转换效率高、系统紧凑、灵活性高等优点。液态金属冷却堆（LMR）与S-CO2布雷顿循环的耦合，充分发挥了两种技术的优势，是核能系统发展的一个有前途的方向。然而，该耦合系统尚处于初步设计阶段。本文对耦合系统的研究进行了综述，重点介绍了耦合系统的设计、液态金属(LM)-S-CO2耦合换热实验与数值模拟以及LM-S-CO2换热管破裂事故。本文对现有研究的成果和不足进行了总结，为今后该领域的研究提供有价值的参考。

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.