scholarly journals Process Heat Exchanger Options for the Advanced High Temperature Reactor

2011 ◽  
Author(s):  
Piyush Sabharwall ◽  
Eung Soo Kim ◽  
Michael McKellar ◽  
Nolan Anderson
Keyword(s):  
High Temperature ◽  
Heat Exchanger ◽  
High Temperature Reactor ◽  
Process Heat

scholarly journals Process Heat Exchanger Options for Fluoride Salt High Temperature Reactor

2011 ◽  
Author(s):  
Piyush Sabharwall ◽  
Eung Soo Kim ◽  
Michael McKellar ◽  
Nolan Anderson
Keyword(s):  
High Temperature ◽  
Heat Exchanger ◽  
Fluoride Salt ◽  
High Temperature Reactor ◽  
Process Heat

scholarly journals Fluoride-Salt-Cooled High-Temperature Reactor (FHR) for Power and Process Heat

2015 ◽  
Author(s):  
Charles Forsberg ◽  
Lin-wen Hu ◽  
Per Peterson ◽  
Kumar Sridharan
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
High Temperature Reactor ◽  
Process Heat

High-Temperature Structural Analysis Model of the Process Heat Exchanger for Helium Gas Loop (II)

2010 ◽  
Vol 34 (10) ◽  
pp. 1455-1462 ◽  
Author(s):  
Kee-Nam Song ◽  
Heong-Yeon Lee ◽  
Chan-Soo Kim ◽  
Seong-Duk Hong ◽  
Hong-Yoon Park
Keyword(s):  
High Temperature ◽  
Heat Exchanger ◽  
Structural Analysis ◽  
Analysis Model ◽  
Helium Gas ◽  
Process Heat ◽  
Gas Loop

scholarly journals Thermal analysis of heat and power plant with high temperature reactor and intermediate steam cycle

2015 ◽  
Vol 36 (1) ◽  
pp. 3-18
Author(s):  
Adam Fic ◽  
Jan Składzień ◽  
Michał Gabriel
Keyword(s):  
Thermal Analysis ◽  
High Temperature ◽  
Heat Exchanger ◽  
Power Plant ◽  
Heat Pump ◽  
Nuclear Reactor ◽  
Temperature Level ◽  
High Temperature Process ◽  
Process Heat ◽  
Steam Cycle

Abstract Thermal analysis of a heat and power plant with a high temperature gas cooled nuclear reactor is presented. The main aim of the considered system is to supply a technological process with the heat at suitably high temperature level. The considered unit is also used to produce electricity. The high temperature helium cooled nuclear reactor is the primary heat source in the system, which consists of: the reactor cooling cycle, the steam cycle and the gas heat pump cycle. Helium used as a carrier in the first cycle (classic Brayton cycle), which includes the reactor, delivers heat in a steam generator to produce superheated steam with required parameters of the intermediate cycle. The intermediate cycle is provided to transport energy from the reactor installation to the process installation requiring a high temperature heat. The distance between reactor and the process installation is assumed short and negligable, or alternatively equal to 1 km in the analysis. The system is also equipped with a high temperature argon heat pump to obtain the temperature level of a heat carrier required by a high temperature process. Thus, the steam of the intermediate cycle supplies a lower heat exchanger of the heat pump, a process heat exchanger at the medium temperature level and a classical steam turbine system (Rankine cycle). The main purpose of the research was to evaluate the effectiveness of the system considered and to assess whether such a three cycle cogeneration system is reasonable. Multivariant calculations have been carried out employing the developed mathematical model. The results have been presented in a form of the energy efficiency and exergy efficiency of the system as a function of the temperature drop in the high temperature process heat exchanger and the reactor pressure.

High-temperature Structural Analysis of Small-scale Prototype of Process Heat Exchanger (III)

2011 ◽  
Vol 35 (2) ◽  
pp. 191-200 ◽  
Author(s):  
Kee-Nam Song ◽  
Heong-Yeon Lee ◽  
Chan-Soo Kim ◽  
Seong-Duk Hong ◽  
Hong-Yoon Park
Keyword(s):  
High Temperature ◽  
Heat Exchanger ◽  
Structural Analysis ◽  
Small Scale ◽  
Process Heat

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%.

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