Practice has proved that nuclear power technology development and operation of nuclear power is a clean, safe and large-scale provided stable power. AP1000 uses a large number of passive safety technologies. Passive residual heat removal system is an important part, in the long-term cooling stage of nuclear reactor normal operating conditions or accident conditions, to prevent the core meltdown. The research of this paper is to solve the long-term discharge of residual heat of the containment in the accident condition of nuclear power plant. Based on the passive heat removal system of AP1000, combined with the heat transfer characteristics and advantages of heat pipes, the PRHR system is further improved on the basis of the present situation, and a conceptual design of passive containment residual heat removal system is proposed. In order to further verify the feasibility of the conceptual design, we make a simplified simulation of small containment test bench to carry out experimental verification and give a detailed experimental design.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5784-7
PROCEEDINGS PAPER
The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design Available to Purchase
Haiqi Qin,
Haiqi Qin
North China Electric Power University, Beijing, China
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Daogang Lu,
Daogang Lu
North China Electric Power University, Beijing, China
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Shengfei Wang
Shengfei Wang
North China Electric Power University, Beijing, China
Search for other works by this author on:
Haiqi Qin
North China Electric Power University, Beijing, China
Daogang Lu
North China Electric Power University, Beijing, China
Shengfei Wang
North China Electric Power University, Beijing, China
Paper No:
ICONE25-67134, V006T08A082; 10 pages
Published Online:
October 17, 2017
Citation
Qin, H, Lu, D, & Wang, S. "The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 6: Thermal-Hydraulics. Shanghai, China. July 2–6, 2017. V006T08A082. ASME. https://doi.org/10.1115/ICONE25-67134
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