scholarly journals Experimental Study on the Residual Heat Removal System in HTR-10

2021 ◽  
Vol 2048 (1) ◽  
pp. 012037
Author(s):  
Jing Li ◽  
Liqiang Wei ◽  
Yanhua Zheng ◽  
Tao Ma ◽  
Xiaoming Chen ◽  
...  
Keyword(s):  
High Temperature ◽  
Experimental Studies ◽  
Heat Removal ◽  
Operating Characteristics ◽  
Pebble Bed ◽  
Operation Conditions ◽  
Heat Removal System ◽  
High Temperature Gas ◽  
Removal System ◽  
Residual Heat

Abstract The 10MW high temperature gas-cooled reactor (HTR-10) is a modular pebble-bed type reactor, of which the inlet and outlet helium temperature are 250 and 700 °C, respectively. It reached to its first criticality in December, 2000, and operated for nearly twenty years successfully. Currently, HTR-10 is the only pebble-bed type high temperature gas-cooled reactor that can operate in the world. To verify the natural circulation operating characteristics and safety features of the passive residual heat removal system, a series of experimental studies have been performed under different operation conditions of HTR-10, which include the performance tests of the passive residual heat removal system under various reactor operating power, different ambient temperature and single loop run mode. According to the data collation and result analysis, it shows that the performance of the residual heat removal system in HTR-10 meets the design and safety requirements.

Transient Study on Sodium Heat Pipe in Passive Heat Removal System of Molten Salt Reactor

2013 ◽  
Author(s):  
Chenglong Wang ◽  
Suizheng Qiu ◽  
Wenxi Tian ◽  
Yingwei Wu ◽  
Guanghui Su
Keyword(s):  
High Temperature ◽  
Molten Salt ◽  
Heat Pipe ◽  
Heat Removal ◽  
Heat Pipes ◽  
Molten Salt Reactor ◽  
Sodium Heat Pipe ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

High temperature heat pipes are effective devices for heat transfer, which are characterized by remarkable advantages in conductivity, isothermality and passivity. It is of significance to apply heat pipes on new concept passive residual heat removal system (PRHRS) of molten salt reactor (MSR). In this paper, the transient performance of high temperature sodium heat pipe is simulated with numerical method in the case of MSR accident. The model of the heat pipe is composed of three conjugate heat transfers, i.e. the vapor space, wick structure and wall. Based on finite element method, the governing equations and boundary conditions are solved by using FORTRAN code to acquire the profiles of the temperature, velocity and pressure for the heat pipe transient operation. The results indicated that high temperature sodium heat pipe had a good operating characteristic and removed the residual heat of fuel salt rapidly under the accident of MSR.

Application of direct passive residual heat removal system to the SMART reactor

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

Experimental study on capability and start-up characteristic of advanced secondary passive residual heat removal system

2021 ◽  
Vol 140 ◽  
pp. 103929
Author(s):  
Qianhua Su ◽  
Haiyan Xu ◽  
Donghua Lu ◽  
Xiaohang Wu ◽  
Xi Yao ◽  
...  
Keyword(s):  
Experimental Study ◽  
Heat Removal ◽  
Start Up ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

Analysis of Passive Residual Heat Removal System at Primary Side when Station Blackout Occurs

2014 ◽  
Vol 986-987 ◽  
pp. 231-234
Author(s):  
Jun Teng Liu ◽  
Qi Cai ◽  
Xia Xin Cao
Keyword(s):  
Nuclear Reactor ◽  
Natural Circulation ◽  
Reactor Core ◽  
Saturation Temperature ◽  
Heat Removal ◽  
Primary Circuit ◽  
Station Blackout ◽  
Heat Removal System ◽  
Removal System ◽  
Residual Heat

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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