Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors

被引：80

作者：

Zhang, Yan ^{[1
]}

Wang, Chenglong ^{[1
]}

Lan, Zhike ^{[2
]}

Wei, Shiying ^{[1
]}

Chen, Ronghua ^{[1
]}

Tian, Wenxi ^{[1
]}

Su, Guanghui ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, Sch Nucl Sci & Technol, Xian 710049, Peoples R China

[2] Nucl Power Inst China, Chengdu 610005, Peoples R China

来源：

RENEWABLE & SUSTAINABLE ENERGY REVIEWS | 2020年 / 120卷

基金：

中国国家自然科学基金;

关键词：

Research review; Lead-based fast reactor; Core/pool/system level; Thermal hydraulics; Lead-based coolants; COOLED FAST-REACTOR; HEAT-TRANSFER EXPERIMENT; SUB-CHANNEL ANALYSIS; GAS ENTRAINMENT; NATURAL CIRCULATION; LIQUID-METALS; SAFETY ANALYSIS; 19-ROD BUNDLE; NUMERICAL-SIMULATION; CONCEPTUAL DESIGN;

D O I：

10.1016/j.rser.2019.109625

中图分类号：

X [环境科学、安全科学];

学科分类号：

08 ; 0830 ;

摘要：

The lead-based reactor is one of the fourth-generation nuclear energy systems with excellent development prospects. It has attracted much attention because of its unique advantages in fuel transmutation and breeding, passive safety, and economic efficiency. In this study, the main features of typical lead-based fast reactors (LFRs) worldwide are reviewed and current challenges in their development are pointed out. Moreover, the research progress in four main thermal-hydraulic aspects is overviewed and discussed, including the flow and heat transfer characteristics of the coolant, thermal-hydraulic analysis of the reactor core, lead pool and reactor system. These aspects are further divided into specific issues according to the developing needs of LFR. For each issue, up-to-date research findings, existing difficulties, and future trends are presented. This study can serve as a reference for the design and thermal-hydraulic analysis of LFRs.

引用

页数：20

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