scholarly journals A Thermohydraulic Code for Low Temperature Nuclear Heating Reactor and Its Passive Residual Heat Removal Systems

2004 ◽  
Vol 41 (12) ◽  
pp. 1255-1270
Author(s):  
Tao ZHOU ◽  
Guanghui SU ◽  
Dounan JIA
Keyword(s):  
Low Temperature ◽  
Heat Removal ◽  
Nuclear Heating Reactor ◽  
Nuclear Heating ◽  
Residual Heat

A Simulation of Small Break Loss of Coolant Accident in Nuclear Heating Reactor Based on RELAP5

2018 ◽  
Author(s):  
Meng Lu ◽  
Heng Xie
Keyword(s):  
Thermal Power ◽  
Heat Removal ◽  
Injection System ◽  
Water Volume ◽  
Nuclear Heating Reactor ◽  
Removal Capacity ◽  
Loss Of Coolant ◽  
Nuclear Heating ◽  
Residual Heat

Nuclear heating reactor is integrated designed without main pump and safety injection system. The loss of coolant accidents are mainly in the form of small break LOCA. As no safety injection system is designed for coolant makeup, the water volume in the reactor vessel is critical since it determines whether the reactor will be submerged during the whole scenario. Therefore, the study on coolant loss in this pool system is indispensable. The RELAP5 code has been developed for best-estimate transient simulation of light water reactor coolant systems during postulated accidents. The long term effect in nuclear heating reactor is important. In this paper we investigated the influential factors on SBLOCA scenario and found the long term residual heat removal capacity is decisive in determining the loss of coolant. The residual heat removal capacity should be greater than 2% of reactor thermal power if ensuring the core submerged in the long run.

Status of District Heating Reactor and its Development Prospects in China

2018 ◽  
Author(s):  
Jing Zhao ◽  
Fei Xie ◽  
Zhihong Liu
Keyword(s):  
Low Temperature ◽  
Nuclear Reactor ◽  
District Heating ◽  
Heating System ◽  
Inherent Safety ◽  
Nuclear Heating Reactor ◽  
New Type ◽  
Nuclear Heating ◽  
Safety Features ◽  
Temperature Heating

Nuclear heating reactor is a new type of power plant that uses nuclear energy as heat source. Low temperature nuclear heating reactor should be the forerunner and main force for developing nuclear heating plant in China. Due to the lower water temperature required by the heating system, this dedicated, non-power generating nuclear reactor works at low temperatures and pressures with inherent safety features. The design, construction and operation of the nuclear heating reactors in various countries in the world were reviewed in this paper, and China’s new demonstration nuclear heating project and NHR-200 low-temperature heating reactor which would be used was discussed in the paper. We put forward the developing route and suggestion for the development of low-temperature heating reactor in China.

Experimental Study on Natural Convection Heat Transfer Outside Tube Bundle in Space Under Low Temperature Difference

2020 ◽  
Author(s):  
Junxiu Xu ◽  
Ming Ding ◽  
Changqi Yan ◽  
Guangming Fan
Keyword(s):  
Heat Transfer ◽  
Heat Exchanger ◽  
Low Temperature ◽  
Tube Bundle ◽  
Convection Heat Transfer ◽  
Heat Removal ◽  
Natural Convection Heat Transfer ◽  
Convection Heat ◽  
Reactor Pool ◽  
Residual Heat

Abstract The Passive Residual Heat Removal System (PRHRS) is very important for the safety of the heating reactor after shutdown. PRHRS is a natural circulation system driven by density difference, therefore, the heat transfer performance of the Passive Residual Heat Removal Heat Exchanger (PRHR HX) has a great impact to the heat transfer efficiency of PRHRS. However, the most research object of PRHR HX is the C-shape heat exchanger at present, which located in In-containment Refueling Water Storage Tank (IRWST). This heat exchanger is mainly used for the PRHRS of nuclear power plants. In the swimming pool-type low-temperature heating reactor (SPLTHR), the PRHR HX is placed in the reactor pool, which the pressure and temperature of the reactor pool are relatively low, and the outside heat transfer mode of tube bundle is mainly natural convection heat transfer. In this study, a miniaturized single-phase pool water cooling system was built to investigate the natural convective heat transfer coefficient of the heat exchanger under the large space and low temperature conditions. The experimental data had been compared with several correlations. The results show that the predicted value of Yang correlation is the closest to the experimental data, which the maximum deviation is about 11%.

The Halting Process of Natural Circulation in Primary Circuit of Low Temperature Nuclear Heating Reactor

2012 ◽  
Vol 512-515 ◽  
pp. 874-877
Author(s):  
Xue Song Zhang ◽  
Zhi Ping Ju ◽  
Jun Rui Shi ◽  
Wei Zhe Li ◽  
Wen Ping Zhou
Keyword(s):  
Low Temperature ◽  
Natural Circulation ◽  
Primary Circuit ◽  
Nuclear Heating Reactor ◽  
Loss Of Coolant Accident ◽  
Burn Out ◽  
Loss Of Coolant ◽  
Nuclear Heating ◽  
Temperature Heating

Fluctuation of security and flux, when natural circulation was halted in primary circuit of low temperature nuclear heating reactor by experiment during small break loss of coolant accident was studied. This is one of disadvantage aspect to such system. The results of this paper was Heated component won’t burn out while SBLOCA in lower cone in low temperature heating reactor. It was valuable suggestions on the development of commercial nuclear heating reactor.

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