scholarly journals Corrigendum to “Study of forced convection nanofluid heat transfer in the automotive cooling system” [Case Stud. Therm. Eng. 16 (2014) 50–61]

2015 ◽  
Vol 5 ◽  
pp. 113
Author(s):  
Adnan M. Hussein ◽  
R.A. Bakar ◽  
K. Kadirgama
Keyword(s):  
Heat Transfer ◽  
Forced Convection ◽  
Cooling System

Study on the Heat Transfer in the Water Pool Type Reactor Cavity Cooling System of the Very High Temperature Gas Cooled Reactor

2005 ◽  
Author(s):  
H. K. Cho ◽  
D. U. Seo ◽  
M. O. Kim ◽  
G. C. Park
Keyword(s):  
Heat Transfer ◽  
Forced Convection ◽  
Cooling System ◽  
Reactor Vessel ◽  
Water Pool ◽  
Cooling Pipe ◽  
Cavity Cooling ◽  
The Heat Transfer Coefficient ◽  
Pool Type ◽  
High Temperature Gas

In the HTGR (High Temperature Gas Cooled Reactor), the Reactor Cavity Cooling System (RCCS) is equipped to remove the heat transferred from the reactor vessel to the structure of the containment. The function of the RCCS is to dissipate the heat from the reactor cavity during normal operation including shutdown. The system also removes the decay heat during the loss of forced convection (LOFC) accident. A new concept of the water pool type RCCS was proposed at Seoul National University. The system mainly consists of two parts, water pool located between the containment and reactor vessel and five trains of air cooling system installed in the water pool. In normal operations, the heat loss from the reactor vessel is transferred into the water pool via cavity and it is removed by the forced convection of air flowing through the cooling pipes. During the LOFC accident, the after heat is passively removed by the water tank without the forced convection of air and the RCCS water pool is designed to provide sufficient passive cooling capacity of the after heat removal for three days. In the present study, experiments and numerical calculations using CFX5.7 for the water pool and cooling pipe were performed to investigate the heat transfer characteristics and evaluate the heat transfer coefficient model of the MARS-GCR (Multi-dimensional Analysis of Reactor Safety for Gas Cooled Reactor Analysis) which was developed for the safety analysis of the gas cooled reactor. From the results of the experiments and CFX calculations, heat transfer coefficients inside the cooling pipe were calculated and those were used for the assessment for the heat transfer coefficient model of the MARS-GCR.

Heat Transfer of Oscillating Fluid through Finned Heat Sink with Top Bypass Clearance

2013 ◽  
Vol 479-480 ◽  
pp. 192-196
Author(s):  
Tzer Ming Jeng ◽  
Sheng Chung Tzeng ◽  
Wei Ting Hsu ◽  
Guan Wei Xu
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Enhancement ◽  
Steady Flow ◽  
Forced Convection ◽  
Flow Rate ◽  
Heat Sink ◽  
Cooling System ◽  
Oscillating Flow ◽  
Transfer Enhancement ◽  
Cooling Performance

This work experimentally investigated the effect of the oscillating flow on the heat transfer enhancement of the finned heat sink with top bypass clearance. The cooling system of the finned heat sink usually employs the steady flow with fixed flow rate to complete the objective of forced convection. This work designed and manufactured a device to oscillate air flow. The experimental results indicate that it would obtain 10~34% heat-transfer increment for the oscillating-flow cases with sufficiently small bypass clearance. It demonstrates that the oscillating flow does promote the cooling performance of finned heat sink.

Heat Transfer Characteristics of Vertical Rectangular Channel Inserting Copper Wire With High Porosity

2009 ◽  
Author(s):  
Akira Honma ◽  
Tetsuaki Takeda
Keyword(s):  
Heat Transfer ◽  
Porous Material ◽  
Forced Convection ◽  
Cooling System ◽  
Copper Wire ◽  
Rectangular Channel ◽  
High Porosity ◽  
Heat Transfer Characteristics ◽  
The Core ◽  
Transfer Characteristics

In the Very-High-Temperature Reactor (VHTR) which is the next generation nuclear reactor system, ceramics and graphite are used as the fuel coating material and the core structural material, respectively. Even if the accident occurs and the reactor power goes up instantly, the temperature of the core will change slowly. This is because the thermal capacity of the core is so large. Therefore, the VHTR system can passively remove the decay heat of the core by natural convection and radiation from the surface of the reactor pressure vessel (RPV). From the view point of the safety characteristic, the passive cooling system should be designed for the VHTR as the best way of the reactor and vessel cooling systems (VCS). So, the gas cooling system by natural convection is the one of the candidate systems for the VCS of the VHTR. This study is to develop the passive cooling system for the VHTR using the vertical rectangular channel inserting porous materials. In general, when the high temperature circular or rectangular channels are cooled by forced convection of gas, there are several methods for enhancement of heat transfer such as attaching radial or spiral fins on a channel surface or inserting twisted tape in a channel. The objective of this study is to investigate heat transfer characteristics by forced convection of porous materials inserted into a rectangular channel with high porosity. In order to obtain the heat transfer characteristics of the one-side heated vertical rectangular channel inserting the porous material, an experiment was carried out. From the results obtained in this experiment, it was found that an amount of removed heat by forced convection using porous material (porosity > 0.996) was about 15% higher than that without the copper wire. Furthermore, the ratio between the amounts of heat removed of the rectangular channel with the porous material and without the porous material increases with increasing temperature of the channel wall.

Thermal Performance of Vertical Rectangular Channel Inserting Copper Wire With High Porosity

2010 ◽  
Author(s):  
Tetsuaki Takeda ◽  
Akira Honma ◽  
Yuta Sugai
Keyword(s):  
Heat Transfer ◽  
Porous Material ◽  
Forced Convection ◽  
Cooling System ◽  
Copper Wire ◽  
Rectangular Channel ◽  
High Porosity ◽  
The Core ◽  
The One ◽  
Passive Cooling System

In the Very-High-Temperature Reactor (VHTR) which is the next generation nuclear reactor system, ceramics and graphite are used as the fuel coating material and the core structural material, respectively. Even if the accident occurs and the reactor power goes up instantly, the temperature of the core will change slowly. This is because the thermal capacity of the core is so large. Therefore, the VHTR system can passively remove the decay heat of the core by natural convection and radiation from the surface of the reactor pressure vessel (RPV). From the view point of the safety characteristic, the passive cooling system should be designed for the VHTR as the best way of the reactor and vessel cooling systems (VCS). So, the gas cooling system by natural convection is the one of the candidate systems for the VCS of the VHTR. This study is to develop the passive cooling system for the VHTR using the vertical rectangular channel inserting porous materials. In general, when the high temperature circular or rectangular channels are cooled by forced convection of gas, there are several methods for enhancement of heat transfer such as attaching radial or spiral fins on a channel surface or inserting twisted tape in a channel. The objective of this study is to investigate heat transfer characteristics by forced convection of porous materials inserted into a rectangular channel with high porosity. In order to obtain the heat transfer characteristics of the one-side heated vertical rectangular channel inserting the porous material, an experiment was carried out. From the results obtained in this experiment, it was found that an amount of removed heat by forced convection using porous material (porosity > 0.996) was about 15% higher than that without the copper wire. Furthermore, the ratio between the amounts of heat removed of the rectangular channel with the porous material and without the porous material increases with increasing temperature of the channel wall.

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