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Bang, In Cheol (방인철)

Department
School of Mechanical, Aerospace and Nuclear Engineering(기계항공및원자력공학부)
Research Interests
Nuclear Thermal-Hydraulics, Nuclear Safety, Nuclear System Design & Analysis, Nanofluids, Critical Heat Flux
Lab
Nuclear Thermal-Hydraulics & Reactor Safety Lab
E-Mail
icbang@unist.ac.kr
Website
http://neths.unist.ac.kr/
This table browses all dspace content
Issue DateTitleAuthor(s)TypeViewAltmetrics
201805Effects of hole patterns on surface temperature distributions in pool boilingSeo, Han; Lim, Yeongjin; Shin, Heungjoo, et alARTICLE109 Effects of hole patterns on surface temperature distributions in pool boiling
201804Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removalKim, Kyung Mo; Bang, In CheolARTICLE110 Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal
201801Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCORMoon. Sung Bo; Lim, Soo Min; Bang, In CheolARTICLE20 Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR
201712Thermal-hydraulic Analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacerPark, Seong Dae; Seo, Han; Jeong, Yeongshin, et alARTICLE19
201712Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancementSon, Gyu Min; Kim, Kyung Mo; Bang, In CheolARTICLE23 Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement
201712Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactorsSeo, Seok Bin; Kim, In Guk; Kim, Kyung Mo, et alARTICLE86 Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors
201712Numerical analysis on spatial universality of similarity technique inside molten salt reactor systemSeo, Seok Bin; Shin, Yukyung; Bang, In CheolARTICLE212 Numerical analysis on spatial universality of similarity technique inside molten salt reactor system
201710Flow visualization and heat transfer performance of annular thermosyphon heat pipeKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin, et alARTICLE416 Flow visualization and heat transfer performance of annular thermosyphon heat pipe
201707Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plantKim, In Guk; Bang, In CheolARTICLE152 Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant
201702Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactorsKim, Kyung Mo; Bang, In CheolARTICLE196 Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors
201702Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMRSeo, Seok Bin; Kim, In Guk; Bang, In CheolARTICLE266 Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR
201612Development of passive in-core cooling system for nuclear safety using hybrid heat pipeKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk, et alARTICLE146 Development of passive in-core cooling system for nuclear safety using hybrid heat pipe
201610Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC depositionKim, Seong Man; Bang, In CheolARTICLE459 Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC deposition
201609Visual Study of Ex-Pin Phenomena for SFR with Metal Fuel Under Initial Phase of Severe Accidents by using SimulantsHeo, Hyo; Park, Seong Dae; Jerng, Dong Wook, et alARTICLE194 Visual Study of Ex-Pin Phenomena for SFR with Metal Fuel Under Initial Phase of Severe Accidents by using Simulants
201608High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networksYun, Hyung Duk; Kwak, Jinsung; Kim, Se-Yang, et alARTICLE440 High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks
201606Natural Circulation with DOWTHERM RP and its MARS Code Implementation for Molten Salt-Cooled ReactorsShin, Yukyung; Seo, Seok Bin; Kim, In Guk, et alARTICLE556 Natural Circulation with DOWTHERM RP and its MARS Code Implementation for Molten Salt-Cooled Reactors
201606Length effect on entrainment limit of large-L/D vertical heat pipeSeo, Joseph; Bang, In Cheol; Lee, Jae-YoungARTICLE250 Length effect on entrainment limit of large-L/D vertical heat pipe
201604Experimental Study on a Novel Liquid Metal Fin Concept Preventing Boiling Critical Heat Flux for Advanced Nuclear Power ReactorsPark, Seong Dae; Kim, Ji Hyun; Bang, In CheolARTICLE460 Experimental Study on a Novel Liquid Metal Fin Concept Preventing Boiling Critical Heat Flux for Advanced Nuclear Power Reactors
201604Comparison of Flooding Limit and Thermal Performance of Annular and Concentric Thermosyphons at Different Fill RatiosKim, Kyung Mo; Bang, In CheolARTICLE214 Comparison of Flooding Limit and Thermal Performance of Annular and Concentric Thermosyphons at Different Fill Ratios
201603Numerical study of in-vessel retention under the gallium-water external reactor vessel cooling system using MARS-LMRKang, Sarah; Park, Seong Dae; Kim, In Guk, et alARTICLE466 Numerical study of in-vessel retention under the gallium-water external reactor vessel cooling system using MARS-LMR

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