BROWSE

사진

  • ResearcherID
  • Scopus

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
201801Numerical analysis on spatial universality of similarity technique inside molten salt reactor systemSeo, Seok Bin; Shin, Yukyung; Bang, In CheolARTICLE4 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 alARTICLE372 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 CheolARTICLE104 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 CheolARTICLE147 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 CheolARTICLE216 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 alARTICLE110 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 CheolARTICLE424 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 alARTICLE161 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 alARTICLE394 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-YoungARTICLE205 Length effect on entrainment limit of large-L/D vertical heat pipe
201606Natural Circulation with DOWTHERM RP and its MARS Code Implementation for Molten Salt-Cooled ReactorsShin, Yukyung; Seo, Seok Bin; Kim, In Guk, et alARTICLE490 Natural Circulation with DOWTHERM RP and its MARS Code Implementation for Molten Salt-Cooled Reactors
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 CheolARTICLE425 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 CheolARTICLE165 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 alARTICLE415 Numerical study of in-vessel retention under the gallium-water external reactor vessel cooling system using MARS-LMR
201603Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage caskJeong, Yeong Shin; Bang, In CheolARTICLE503 Hybrid heat pipe based passive cooling device for spent nuclear fuel dry storage cask
201602Effects of graphene oxide nanofluids on heat pipe performance and capillary limitsKim, Kyung Mo; Bang, In CheolARTICLE371 Effects of graphene oxide nanofluids on heat pipe performance and capillary limits
201602Revisiting the Rayleigh-Taylor instability and critical heat flux with R-123 for different heater sizes and pressuresSeo, Han; Bang, In CheolARTICLE229 Revisiting the Rayleigh-Taylor instability and critical heat flux with R-123 for different heater sizes and pressures
201602Hybrid Graphene and Single-Walled Carbon Nanotube Films for Enhanced Phase-Change Heat TransferSeo, Han; Yun, Hyung Deok; Kwon, Soon-Yong, et alARTICLE245 Hybrid Graphene and Single-Walled Carbon Nanotube Films for Enhanced Phase-Change Heat Transfer
201601Adoption of nitrogen power conversion system for small scale ultra-long cycle fast reactor eliminating intermediate sodium loopSeo, Seok Bin; Seo, Han; Bang, In CheolARTICLE253 Adoption of nitrogen power conversion system for small scale ultra-long cycle fast reactor eliminating intermediate sodium loop
201601Performance of annular flow path heat pipe with a polymer insert controlling compactness for energy applicationsKim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin, et alARTICLE402 Performance of annular flow path heat pipe with a polymer insert controlling compactness for energy applications

MENU