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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
Website
http://neths.unist.ac.kr/
This table browses all dspace content
Issue DateTitleAuthor(s)TypeViewAltmetrics
201812Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coatingLee, Min Ho; Heo, Hyo; Bang, In CheolARTICLE29 Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coating
201810Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal managementKim, In Guk; Bang, In CheolARTICLE9 Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal management
201807Natural convection heat transfer characteristics of molten salt with internal heat generationJeong, Yeong Shin; Seo, Seok Bin; Bang, In CheolARTICLE160 Natural convection heat transfer characteristics of molten salt with internal heat generation
201806Study on flow characteristics of high-Pr heat transfer fluid near the wall in a rectangular natural circulation loopShin, Yukyung; Seo, Seok Bin; Bang, In CheolARTICLE99 Study on flow characteristics of high-Pr heat transfer fluid near the wall in a rectangular natural circulation loop
201805Effects of hole patterns on surface temperature distributions in pool boilingSeo, Han; Lim, Yeongjin; Shin, Heungjoo, et alARTICLE425 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 CheolARTICLE336 Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal
201804Thermal-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, Yeong Shin, et alARTICLE211 Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer
201803Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancementSon, Gyu Min; Kim, Kyung Mo; Bang, In CheolARTICLE211 Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement
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 CheolARTICLE205 Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR
201712Numerical analysis on spatial universality of similarity technique inside molten salt reactor systemSeo, Seok Bin; Shin, Yukyung; Bang, In CheolARTICLE430 Numerical analysis on spatial universality of similarity technique inside molten salt reactor system
201712Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactorsSeo, Seok Bin; Kim, In Guk; Kim, Kyung Mo, et alARTICLE260 Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors
201710Flow visualization and heat transfer performance of annular thermosyphon heat pipeKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin, et alARTICLE536 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 CheolARTICLE280 Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant
201702Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMRSeo, Seok Bin; Kim, In Guk; Bang, In CheolARTICLE433 Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR
201702Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactorsKim, Kyung Mo; Bang, In CheolARTICLE341 Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors
201612Development of passive in-core cooling system for nuclear safety using hybrid heat pipeKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk, et alARTICLE238 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 CheolARTICLE554 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 alARTICLE354 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 alARTICLE670 High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks
201606Length effect on entrainment limit of large-L/D vertical heat pipeSeo, Joseph; Bang, In Cheol; Lee, Jae-YoungARTICLE373 Length effect on entrainment limit of large-L/D vertical heat pipe

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