Preliminary feasibility analysis of Heat Pipe Cooled Bimodal Space Nuclear Reactor

2021 ◽  
pp. 103817
Author(s):  
Xiaoyan Tian ◽  
Huaqi Li ◽  
Duoyu Jiang ◽  
Lei Zhu ◽  
Sen Chen ◽  
...  
Keyword(s):  
Heat Pipe ◽  
Nuclear Reactor ◽  
Feasibility Analysis

scholarly journals Preliminary quantitative feasibility analysis of proposed Thorium-based nuclear reactor

2019 ◽  
Vol 555 ◽  
pp. 012006
Author(s):  
Anas Muhamad Pauzi ◽  
Azril Wasim Abdul Wahid ◽  
Juniza Md Saad
Keyword(s):  
Nuclear Reactor ◽  
Feasibility Analysis

Numerical analysis of segmented thermoelectric generators applied in the heat pipe cooled nuclear reactor

2021 ◽  
pp. 117949
Author(s):  
Yin ZHANG ◽  
Kailun GUO ◽  
Chenglong WANG ◽  
Simiao Tang ◽  
Dalin ZHANG ◽  
...  
Keyword(s):  
Numerical Analysis ◽  
Heat Pipe ◽  
Nuclear Reactor ◽  
Thermoelectric Generators

Simulation of a High-Temperature Modular Reactor (HTMR) for Power and Coal-to-Liquid Fuel-Cogeneration Plant

2014 ◽  
Author(s):  
Mubenga Carl Tshamala ◽  
Robert T. Dobson
Keyword(s):  
Power Generation ◽  
High Temperature ◽  
Heat Exchanger ◽  
Heat Pipe ◽  
Superheated Steam ◽  
Nuclear Reactor ◽  
Electrical Power ◽  
Cogeneration Plant ◽  
Process Heat ◽  
Pipe Heat

Traditionally nuclear reactor power plants have been optimized for electrical power generation only. In the light of the ever-rising cost of ever-dwindling fossil fuel resources as well the global polluting effects and consequences of their usage, the use of nuclear energy for process heating is becoming increasingly attractive. In this study the use of a so-called cogeneration plant in which a nuclear reactor energy source is simulated using basic equations for the simultaneous production of superheated steam for electrical power generation and process heat, is considered and analyzed. A novel heat pipe heat exchanger is used to generate superheated steam for the process heat which is, in this case, a coal-to-liquid process (CTL). Natural circulation of sodium, via a thermo-syphon, is used in the heat pipe heat exchanger to transfer heat from the hot stream to the cold. The superheated steam for power generation is generated in a separate once-through helical coil steam generator. A 750 °C, 7 MPa helium cooled high-temperature modular reactor (HTMR) has been considered to simultaneously provide steam at 540 °C, 13.5 MPa for the power unit and steam at 430 °C, 4 MPa for a CTL production plant. The simulation and dynamic control of such a cogeneration plant is considered. In particular, a theoretical model of the plant will be simulated with the aim of predicting the transient and dynamic behavior of the HTMR in order to provide guideline for the control of the plant under various operating conditions. It was found that the simulation model captured the behavior of the plant reasonably well and it is recommended that it could be used in the detailed design of plant control strategies. It was also found that using a 1500 MW-thermal HTMR the South African contribution to global pollution can be reduced by 1.58%.

Experimental Demonstration of a Heat Pipe–Stirling Engine Nuclear Reactor

2014 ◽  
Vol 188 (3) ◽  
pp. 229-237 ◽  
Author(s):  
David I. Poston ◽  
Patrick R. McClure ◽  
David D. Dixon ◽  
Marc A. Gibson ◽  
Lee S. Mason
Keyword(s):  
Heat Pipe ◽  
Nuclear Reactor ◽  
Stirling Engine ◽  
Experimental Demonstration

scholarly journals Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system

2020 ◽  
Vol 52 (1) ◽  
pp. 19-26 ◽  
Author(s):  
Chenglong Wang ◽  
Hao Sun ◽  
Simiao Tang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
Heat Pipe ◽  
Nuclear Reactor ◽  
Reactor System ◽  
Hydraulic Analysis ◽  
Thermal Hydraulic Analysis

Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor

2020 ◽  
Vol 142 ◽  
pp. 107412
Author(s):  
Xiao Liu ◽  
Ran Zhang ◽  
Yu Liang ◽  
Simiao Tang ◽  
Chenglong Wang ◽  
...  
Keyword(s):  
Heat Pipe ◽  
Nuclear Reactor

Experimental investigation on the heat transfer performance of high-temperature potassium heat pipe for nuclear reactor

2021 ◽  
Vol 378 ◽  
pp. 111182
Author(s):  
Zhixing Tian ◽  
Xiao Liu ◽  
Chenglong Wang ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Experimental Investigation ◽  
High Temperature ◽  
Heat Pipe ◽  
Heat Transfer Performance ◽  
Nuclear Reactor ◽  
Transfer Performance
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