Accident analyses for china pressurizer reactor with an innovative conceptual design of passive residual heat removal system

2014 ◽  
Vol 272 ◽  
pp. 45-52 ◽  
Author(s):  
Mingjun Wang ◽  
Dalin Zhang ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
Guanghui Su
Author(s):  
Haiqi Qin ◽  
Daogang Lu ◽  
Shengfei Wang

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.


2021 ◽  
Author(s):  
Shijia Xu ◽  
Qinglong Wen ◽  
Shenhui Ruan ◽  
Ningning Zhao ◽  
Yukang Liu

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.


2016 ◽  
Vol 89 ◽  
pp. 56-62 ◽  
Author(s):  
Yeon-Sik Kim ◽  
Sung-Won Bae ◽  
Seok Cho ◽  
Kyoung-Ho Kang ◽  
Hyun-Sik Park

2021 ◽  
Vol 140 ◽  
pp. 103929
Author(s):  
Qianhua Su ◽  
Haiyan Xu ◽  
Donghua Lu ◽  
Xiaohang Wu ◽  
Xi Yao ◽  
...  

2014 ◽  
Vol 986-987 ◽  
pp. 231-234
Author(s):  
Jun Teng Liu ◽  
Qi Cai ◽  
Xia Xin Cao

This paper regarded CNP1000 power plant system as the research object, which is the second-generation half Nuclear Reactor System in our country, and tried to set Westinghouse AP1000 passive residual heat removal system to the primary circuit of CNP1000. Then set up a simulation model based on RELAP5/MOD3.2 program to calculate and analyze the response and operating characteristic of passive residual heat removal system on assumption that Station Blackout occurs. The calculation has the following conclusions: natural circulation was quickly established after accident, which removes core residual heat effectively and keep the core safe. The residual heat can be quickly removed, and during this process the actual temperature was lower than saturation temperature in reactor core.


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