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

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.

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
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