scholarly journals Analysis of passive residual heat removal system in AP1000 nuclear power plant

2019 ◽  
Vol 214 ◽  
pp. 012095
Author(s):  
J Sierchuła
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Heat Removal ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

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 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.

Failure analysis of elbow pipe cracking in a residual heat-removal system of a nuclear power plant

2018 ◽  
Vol 84 ◽  
pp. 101-108 ◽  
Author(s):  
Yin Kaiju ◽  
Tang Wu ◽  
Zhang Min ◽  
Xiao Jun ◽  
Song Pengcheng ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Failure Analysis ◽  
Nuclear Power ◽  
Heat Removal ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Development and investigation of the regulator of the passive heat-removal system for the Kudankulam nuclear power plant (India)

Atomic Energy ◽  
2007 ◽  
Vol 102 (1) ◽  
pp. 54-59
Author(s):  
V. I. Polunichev ◽  
G. P. Shumailov ◽  
P. A. Gorbunov ◽  
M. M. Grigor’ev ◽  
A. A. Plakseev ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Heat Removal ◽  
Heat Removal System ◽  
Removal System

Experimental studies of thermohydraulic processes for the passive heat-removal system at the Leningradskaya nuclear power plant

Atomic Energy ◽  
2010 ◽  
Vol 108 (5) ◽  
pp. 335-342 ◽  
Author(s):  
V. O. Kukhtevich ◽  
V. V. Bezlepkin ◽  
S. V. Svetlov ◽  
V. G. Sidorov ◽  
S. B. Alekseev ◽  
...  
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Experimental Studies ◽  
Heat Removal ◽  
Heat Removal System ◽  
Removal System

Transformable Elements of the Heat Removal System of Space Nuclear Power Plant

2020 ◽  
Vol 63 (2) ◽  
pp. 317-322
Author(s):  
M. A. Ladyko ◽  
G. V. Volchkov ◽  
A. G. Vystavkin ◽  
A. V. Matveev
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Heat Removal ◽  
Space Nuclear Power ◽  
Heat Removal System ◽  
Removal System

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.

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