Search results for: In Cheol Bang

Items from 1 to 20 out of 62 results

article

Effective energy management design of spent fuel dry storage based on hybrid control rod‐heat pipe

Kyung Mo Kim, In Cheol Bang

International Journal of Energy Research > 45 > 2 > 2160 - 2176

Spent fuel dry storage cask, which stores the spent fuel from wet storage facility to final processing, has been developed and managed. Even though thermal management mechanisms of dry storage casks secure the thermal integrity of the cask, improvement of thermal management capacity of dry storage cask would enhance thermal margin against unforeseen off‐normal conditions with increasing specific storage...

article

Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

Yeong Shin Jeong, Eric Cervi, Antonio Cammi, Hisashi Ninokata, more

International Journal of Energy Research > 44 > 5 > 3934 - 3953

The strongly coupled behaviors between neutronics and thermal‐hydraulics of liquid‐fueled molten salt reactors make it difficult to evaluate system behaviors, due to the transport of precursors along moving fuel. Extending an adjoint‐based method on the multiphysics approach, different assumptions on temperature dependencies of nuclear and thermophysical properties of salt are included in the local...

article

Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal management

In Guk Kim, In Cheol Bang

Energy Conversion and Management > 2018 > 173 > C > 233-243

The global warming resulting from the emission of the greenhouse gases has led to tightened restrictions on the use of fossil. Therefore, renewable energy for new energy sources is being widely investigated. However, renewable energy has limitations such as location, environmental conditions, and the potential construction of a new electricity grid. Spent nuclear fuel (SNF) is one of the potential...

article

Effects of hole patterns on surface temperature distributions in pool boiling

Han Seo, Yeongjin Lim, Heungjoo Shin, In Cheol Bang

International Journal of Heat and Mass Transfer > 2018 > 120 > C > 587-596

This paper presents the results of a study on critical heat flux (CHF) and boiling heat transfer (BHT) enhancements of a heating surface modified through the addition of holes of various dimensions. A layer of indium tin oxide was used as the heater material and holes of various patterns were incorporated onto the heating surfaces. The hole sizes and positions were controlled for precision using conventional...

article

Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal

Kyung Mo Kim, In Cheol Bang

International Journal of Heat and Mass Transfer > 2018 > 119 > C > 472-483

In this study, a new type of thermosyphon, the hybrid heat pipe-control rod, was suggested as a passive decay heat removal device in nuclear facilities. A self-pressurization strategy, which is a passive pressure control mechanism, was introduced to achieve high operating pressure in the hybrid heat pipe, because most nuclear facilities are under high-pressure and high-temperature conditions. In the...

article

Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement

Gyu Min Son, Kyung Mo Kim, In Cheol Bang

International Journal of Heat and Mass Transfer > 2018 > 118 > C > 890-899

In Fukushima accident, zirconium cladding was rapidly oxidized with high temperature steam, which ultimately led to hydrogen explosion. To overcome materialistic limitation, accident tolerant fuel (ATF) was suggested to improve safety response of nuclear power plants during accidents by modifying cladding surface with various coating materials. When chrome was coated on cladding surface, it showed...

article

Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors

Seok Bin Seo, In Guk Kim, Kyung Mo Kim, Yeong Shin Jeong, more

Annals of Nuclear Energy > 2018 > 111 > C > 554-567

After the Fukushima accident, the installation of passive safety systems for nuclear power plants becomes necessary as protection against external power failures. Recently, an innovative safety system was introduced by employing a hybrid heat-pipe concept asa Passive IN-core Cooling system (PINCs). The hybrid heat-pipe concept employs the combination of a control rod and a heat pipe to passively shutdown...

article

Numerical analysis on spatial universality of similarity technique inside molten salt reactor system

Seok Bin Seo, Yukyung Shin, In Cheol Bang

International Journal of Heat and Mass Transfer > 2018 > 116 > C > 569-580

To compensate the difficulties in the study on a thermal-hydraulic system in a full scale, a similarity technique has been developed to predict the thermal characteristics of fluid in the full-scale system under smaller and simpler conditions. Then the feasibility of using simulant fluid for various MSR systems are numerically tested based on the similarity technique in this study. The utilization...

article

Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR

Sung Bo Moon, Soo Min Lim, In Cheol Bang

International Journal of Energy Research > 42 > 1 > 104 - 116

Hydrogen explosion is one of the most dangerous accident phenomena in both nuclear fusion and fission reactor. In the typical fusion reactor, tritium and deuterium are fuel elements for fusion reaction, and they exist in condensed state around the cryo‐pump in the normal operation condition. In the accident situation, increasing heat transfer system temperature can mobilize lots of tritium in the...

article

Flow visualization and heat transfer performance of annular thermosyphon heat pipe

In Guk Kim, Kyung Mo Kim, Yeong Shin Jeong, In Cheol Bang

Applied Thermal Engineering > 2017 > 125 > C > 1456-1468

To clearly understand the operation phenomena of thermosyphon heat pipes, current study experimentally investigated the visualization of the operation and limit conditions for a water-filled thermosyphon as well as its thermal performance. The flow patterns and behaviors at the evaporator region are essential for understanding the heat transfer mechanism of heat pipes. Flow visualization was conducted...

article

Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant

In Guk Kim, In Cheol Bang

Experimental Thermal and Fluid Science > 2017 > 85 > C > 266-278

Safety systems in nuclear power plants have become an important research topic owing to the significant impact of nuclear disasters. Herein, a passive in-core cooling system is proposed to delay the time of fuel melting and to enhance the safety of nuclear power plants during station blackout accidents. The passive in-core cooling system consist of a hydraulic control rod drive mechanism and a hybrid...

article

Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors

Kyung Mo Kim, In Cheol Bang

Applied Thermal Engineering > 2017 > 112 > C > 560-571

In this paper, a hybrid heat pipe is proposed for use in advanced nuclear power plants as a passive heat transfer device. The hybrid heat pipe combines the functions of a heat pipe and a control rod to simultaneously remove the decay heat generated from the core and shutdown the reactor under accident conditions. Thus, the hybrid heat pipe contains a neutron absorber in the evaporator section, which...

article

Risk‐reduction of passive decay heat removal system by using gallium‐water for UCFR and SMR

Seok Bin Seo, In Guk Kim, In Cheol Bang

International Journal of Energy Research > 41 > 2 > 207 - 219

Employing a gallium‐based passive decay heat removal system (PDHRS), which enables the use of water as an ultimate heat sink, was proposed for the UCFR‐100. The gallium‐based PDHRS has replaced the previous sodium‐based PDHRS. To evaluate the safety and thermal performance of the gallium‐based PDHRS, safety analysis and heat exchanger tests were performed. The safety analysis, using both deterministic...

article

Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC deposition

Seong Man Kim, In Cheol Bang

Annals of Nuclear Energy > 2016 > 96 > C > 12-18

In a nuclear power plant, chalk river unidentified deposit (CRUD) is known as a deposit that is composed of corrosion and oxidation materials. It has a porous structure, which combines with boron that is injected into the coolant for controlling power levels. The buildup of corrosion products on the fuel cladding surface has proven to be particularly significant for both BWRs and PWRs. The high temperature...

article

High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks

Hyung Duk Yun, Jinsung Kwak, Se-Yang Kim, Han Seo, more

Journal of Alloys and Compounds > 2016 > 675 > C > 37-45

Indium tin oxide-free, flexible transparent electrodes (TEs) are crucial for the future commercialization of flexible and wearable electronics. While carbon-based TEs containing carbon nanotube (CNT) networks show promise, they usually exhibit poor dispersion properties, limiting their performance and practicality. In this study, we report a highly efficient and bending durable all-carbon composite...

article

Natural circulation with DOWTHERM RP and its MARS code implementation for molten salt‐cooled reactors

Yukyung Shin, Seok Bin Seo, In Guk Kim, In Cheol Bang

International Journal of Energy Research > 40 > 8 > 1122 - 1133

Recently, molten salt has received attention as a promising coolant for advanced nuclear reactors, especially for fluoride salt‐cooled high‐temperature reactor. The heat transfer characteristics of molten salt provide great advantages for application as a primary coolant, because of its superior performance in terms of sustainability, economics, safety, and reliability compared with gas coolant. However,...

article

Length effect on entrainment limit of large-L/D vertical heat pipe

Joseph Seo, In-Cheol Bang, Jae-Young Lee

International Journal of Heat and Mass Transfer > 2016 > 97 > C > 751-759

Heat pipes, which are heat-transfer devices of high thermal conductance, have been studied intensively because of their applicability and efficiency. However, only a small number of studies have been conducted on relatively long heat pipes. Here, the thermal hydraulic characteristics of a long heat pipe are studied. In particular, the thermal performance of the heat pipe and the entrainment limit,...

article

Comparison of flooding limit and thermal performance of annular and concentric thermosyphons at different fill ratios

Kyung Mo Kim, In Cheol Bang

Applied Thermal Engineering > 2016 > 99 > C > 179-188

A passive in-core cooling system (PINCs) based on hybrid heat pipe can be adopted to enhance the passive safety of advanced nuclear power plants. A hybrid heat pipe is a heat transfer device that takes the dual roles of neutron absorption and heat removal by combining the functions of a heat pipe and a control rod. To observe the effect of neutron absorber material inside the heat pipe and fill ratio...

article

Experimental study on a novel liquid metal fin concept preventing boiling critical heat flux for advanced nuclear power reactors

Seong Dae Park, Ji Hyun Kim, In Cheol Bang

Applied Thermal Engineering > 2016 > 98 > C > 743-755

The public has expressed concern about the safety of a nuclear power plant after the Fukushima Daiichi nuclear disaster that was caused by a tsunami on March 11, 2011. There are enough safety systems in nuclear power plants, but the accident occurred owing to an expected, complex natural disaster. If inevitable nuclear accidents take place, we have to consider the best way to mitigate public damage...

article

Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage cask

Yeong Shin Jeong, In Cheol Bang

Applied Thermal Engineering > 2016 > 96 > C > 277-285

Conventional dry storage facilities for spent nuclear fuel (SNF) were designed to remove decay heat through the natural convection of air, but this method has limited cooling capacity and a possible re-criticality accident in case of flooding. To enhance the safety and capacity of dry storage cask of SNF, hybrid heat pipe-based passive cooling device was suggested. Heat pipe is an excellent passive...

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Search results for: In Cheol Bang

Effective energy management design of spent fuel dry storage based on hybrid control rod‐heat pipe

Adjoint‐based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor

Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal management

Effects of hole patterns on surface temperature distributions in pool boiling

Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal

Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement

Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors

Numerical analysis on spatial universality of similarity technique inside molten salt reactor system

Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR

Flow visualization and heat transfer performance of annular thermosyphon heat pipe

Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant

Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors

Risk‐reduction of passive decay heat removal system by using gallium‐water for UCFR and SMR

Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC deposition

High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks

Natural circulation with DOWTHERM RP and its MARS code implementation for molten salt‐cooled reactors

Length effect on entrainment limit of large-L/D vertical heat pipe

Comparison of flooding limit and thermal performance of annular and concentric thermosyphons at different fill ratios

Experimental study on a novel liquid metal fin concept preventing boiling critical heat flux for advanced nuclear power reactors

Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage cask

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