The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design

2017 ◽  
Author(s):  
Haiqi Qin ◽  
Daogang Lu ◽  
Shengfei Wang
Keyword(s):  
Conceptual Design ◽  
Nuclear Power ◽  
Large Scale ◽  
Heat Removal ◽  
Operating Conditions ◽  
Concept Design ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

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.

Nuclear Power Plant Passive Residual Heat Removal System Design and Simulation

2013 ◽  
Author(s):  
Xiao Yuan ◽  
Minjun Peng ◽  
Genglei Xia
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Heat Removal ◽  
Primary Circuit ◽  
Two Phase ◽  
Pressurized Water ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

The passive safety systems employed in the design of pressurized water reactor (PWR) can accomplish the inherent safety functions and mitigate the consequences of the postulated accidents. In this paper, a passive residual heat removal system (PRHRs) is designed for a certain nuclear power plant. The RELAP5/MOD3.4 code was used to analyze the operation characteristics of the PRHRs. It shows the PRHRs could remove the decay heat from the primary loop effectively, and the single-phase and two-phase natural circulations could respectively establish in the primary circuit and the PRHRs circuit.

scholarly journals Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000

2021 ◽  
Vol 2021 ◽  
pp. 1-6
Author(s):  
Feng Li ◽  
Yazhe Lu ◽  
Xiao Chu ◽  
Qiang Zheng ◽  
Guanghao Wu
Keyword(s):  
Nuclear Power ◽  
Natural Circulation ◽  
Heat Removal ◽  
Two Phase ◽  
Safe State ◽  
Station Blackout ◽  
Run Test ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two-phase natural circulation principle, the system is designed to bring out long-term core residual heat after an accident to ensure that the reactor is in a safe state. The steady-state characteristic test and transient start and run test of the PRS were carried out on the integrated experiment bench named ESPRIT. The experiment results show that the PRS can establish natural circulation and discharge residual heat of the first loop. China’s Fuqing no. 5 nuclear power plant completed the installation of the PRS in September 2019 and carried out commissioning work in October. This debugging is the first real-world debugging of the new design. This paper introduces the design process of the PRS debugging scheme.

scholarly journals Study on natural convection heat transfer in a closed cavity with hot and cold tubes

2021 ◽  
Vol 104 (2) ◽  
pp. 003685042110209
Author(s):  
Jiyu Zheng ◽  
Liang Zhang ◽  
Hai Yu ◽  
Yilong Wang ◽  
Tong Zhao
Keyword(s):  
Heat Transfer ◽  
Natural Convection ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Heat Removal ◽  
Closed Cavity ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Laminar natural convection with a pair of hot and cold tube in a closed cubic cavity is carried out. This configuration can be founded in performance of nuclear power plant containment passive residual heat removal system. The basic government aquations are sloved by means of finite volume method. The effect of Ra number (103–106), shape of tube and spatial position on local and mean heat transfer characteristics is studied. It is found that the Nu number increased when raising Ra number. The Nu number is higher when the shapes are circle and triangle. In adddition, it is founded that the heat transfer has a better effect when the cold tube locates above the hot tube among the five spatial positions. The results provides theoretical basis for performance of nuclear power plant containment passive residual heat removal system.

Conceptual Design and Evaluation of Residual Heat Removal System for Small Lead-Bismuth Fast Reactor

2021 ◽  
Author(s):  
Shijia Xu ◽  
Qinglong Wen ◽  
Shenhui Ruan ◽  
Ningning Zhao ◽  
Yukang Liu
Keyword(s):  
Mass Flow Rate ◽  
Conceptual Design ◽  
Mass Flow ◽  
Flow Rate ◽  
Fast Reactor ◽  
Heat Removal ◽  
The Core ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Abstract A high efficient and reliable residual heat removal system (RHRS), which is of great importance in the development of Lead-Bismuth Cooled Fast Reactor (LBFR), was conceptually designed in present study. Based on the design of the RHRS and LBFR, the RELAP5 4.0 code is used to model the system, and then the numerical calculation of steady and transient state was carried out to obtain the important thermal-hydraulic characteristic parameters. Meanwhile, the variations of the parameters were obtained during the transient process, such as the fuel cladding temperature and the natural circulation mass flow rate. The results show that the mass flow rate of the core finally stabilizes at 3.9 kg/s, which is about 1.35% of the rated flow. The peak cladding temperature is less than 750.3 K within 72 h during the whole process, which is far below the temperature safety limit. Therefore, it can be considered that the RHRS can successfully remove the core decay heat of LBFR. This research lays a solid technical foundation for the conceptual design of the RHRS.

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