Review of recent research on heat pipe cooled reactor

被引：15

作者：

Wang, Bo ^{[1
,2
]}

Xu, Shunhao ^{[1
,2
]}

Wang, Bin ^{[3
]}

Wang, Weibing ^{[1
,2
]}

Liu, Yongchao ^{[1
,2
]}

Hu, Shaochun ^{[1
,2
]}

Zhang, Jiayi ^{[1
]}

Wang, Mengyao ^{[4
]}

机构：

[1] Harbin Engn Univ, Coll Nucl Sci & Technol, Harbin 150001, Peoples R China

[2] Harbin Engn Univ, Heilongjiang Prov Key Lab Nucl Power Syst & Equipm, Harbin 150001, Peoples R China

[3] NingXia North FLK Technol Co Ltd, Yinchuan 750205, Ning Xia, Peoples R China

[4] Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China

来源：

NUCLEAR ENGINEERING AND DESIGN | 2023年 / 415卷

关键词：

Heat pipe cooled reactor; Heat pipe; Physical properties; Accident work conditions; NUMERICAL-SIMULATION; NUCLEAR; SYSTEM; CORE; PERFORMANCE; DESIGN; CYCLE;

D O I：

10.1016/j.nucengdes.2023.112679

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

With the development of the fourth-generation nuclear power technology, heat pipe cooled reactor (HPCR) plays an important role in achieving carbon neutrality and actively and orderly developing nuclear power. In this paper, the HPCR will be reviewed. Firstly, a basic introduction of the HPCR and heat pipes will be given. Then, the research status of the HPCR is introduced according to the application. After that, the research status of HPCR in physical and thermal hydraulic characteristics is introduced. Finally, some discussions and recommendations are put forward for the further study.

引用

页数：20

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