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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
2020-01Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assemblyJeong, Yeong Shin; Kim, Ji Yong; Bang, In CheolARTICLE34 Enhanced heat transfer and reduced pressure loss with U-pattern of helical wire spacer arrangement for liquid metal cooled-fast reactor fuel assembly
2019-09CHF enhancement partitioning based on surface wettability and porosity on CeO2 nanoparticle coated surfaceKim, J.Y.; Bang, In CheolARTICLE29 CHF enhancement partitioning based on surface wettability and porosity on CeO2 nanoparticle coated surface
2019-08Phenomenological study on the Ex-pin phenomena in the initial phase of HCDA on metal-fueled SFR using simulantLee, Min Ho; Heo, Hyo; Jerng, Dong Wook, et alARTICLE449 Phenomenological study on the Ex-pin phenomena in the initial phase of HCDA on metal-fueled SFR using simulant
2019-03Acoustic analysis on the dynamic motion of vapor-liquid interface for the identification of boiling regime and critical heat fluxSeo, Seok Bin; Bang, In CheolARTICLE185 Acoustic analysis on the dynamic motion of vapor-liquid interface for the identification of boiling regime and critical heat flux
2018-12Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coatingLee, Min Ho; Heo, Hyo; Bang, In CheolARTICLE206 Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coating
2018-10Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal managementKim, In Guk; Bang, In CheolARTICLE136 Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal management
2018-07Natural convection heat transfer characteristics of molten salt with internal heat generationJeong, Yeong Shin; Seo, Seok Bin; Bang, In CheolARTICLE425 Natural convection heat transfer characteristics of molten salt with internal heat generation
2018-06Study on flow characteristics of high-Pr heat transfer fluid near the wall in a rectangular natural circulation loopShin, Yukyung; Seo, Seok Bin; Bang, In CheolARTICLE284 Study on flow characteristics of high-Pr heat transfer fluid near the wall in a rectangular natural circulation loop
2018-05Effects of hole patterns on surface temperature distributions in pool boilingSeo, Han; Lim, Yeongjin; Shin, Heungjoo, et alARTICLE691 Effects of hole patterns on surface temperature distributions in pool boiling
2018-04Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removalKim, Kyung Mo; Bang, In CheolARTICLE544 Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal
2018-04Thermal-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 alARTICLE398 Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer
2018-03Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancementSon, Gyu Min; Kim, Kyung Mo; Bang, In CheolARTICLE387 Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement
2018-01Numerical analysis on spatial universality of similarity technique inside molten salt reactor systemSeo, Seok Bin; Shin, Yukyung; Bang, In CheolARTICLE684 Numerical analysis on spatial universality of similarity technique inside molten salt reactor system
2018-01Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactorsSeo, Seok Bin; Kim, In Guk; Kim, Kyung Mo, et alARTICLE498 Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors
2018-01Analysis 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 CheolARTICLE420 Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR
2017-10Flow visualization and heat transfer performance of annular thermosyphon heat pipeKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin, et alARTICLE721 Flow visualization and heat transfer performance of annular thermosyphon heat pipe
2017-07Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plantKim, In Guk; Bang, In CheolARTICLE455 Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant
2017-02Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactorsKim, Kyung Mo; Bang, In CheolARTICLE536 Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors
2017-02Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMRSeo, Seok Bin; Kim, In Guk; Bang, In CheolARTICLE673 Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR
2016-12Development of passive in-core cooling system for nuclear safety using hybrid heat pipeKim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk, et alARTICLE392 Development of passive in-core cooling system for nuclear safety using hybrid heat pipe

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