NUCLEAR POWER PLANT PASSIVE RESIDUAL HEAT REMOVAL SYSTEM DESIGN AND SIMULATION

被引:0
|
作者
Yuan Xiao [1 ]
Peng Minjun [1 ]
Xia Genglei [1 ]
机构
[1] Harbin Engn Univ, Coll Nucl Sci & Technol, Key Discipline Lab Nucl Safety & Simulat Technol, Harbin 150001, Heilongjiang, Peoples R China
关键词
Natural Circulation; Passive Safety Reactor; Residual Heat Removal; Design and Simulation;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
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.
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页数:6
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