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Bang, In Cheol (방인철)

Department
Department of Nuclear Engineering(원자력공학과)
Website
http://neths.unist.ac.kr/
Lab
Nuclear Thermal Hydraulics and Reactor Safety Lab. (원자력 열수력 및 안전 실험실)
Research Keywords
원자력시스템, 원자력안전, 원자력계통 설계 및 안전해석, 나노유체, 임계열유속, Nuclear System Design, Nuclear Safety, CHF, Boiling Enhancement technology, Nanofluid
Research Interests
The lab supports to fill important needs for more thorough treatments of the processes of energy (heat) generation in nuclear processes, the transport of that energy by the reactor coolant to the power cycle, and the limitations imposed by the transport mechanism on the design of nuclear reactor. The research has been focused on the development of enhanced heat transfer technologies in nuclear fission and fusion systems, and the study of fundamental thermal-hydraulic phenomena ultimately related to nuclear safety and economics. The lab is also interested in development of advanced engineered features for nuclear safety systems or safer nuclear reactor based on the innovative ideas. The works are engaged in both experimental and analytical research and development (R&D).
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Issue DateTitleAuthor(s)TypeViewAltmetrics
2011-01Investigation of viscosity and thermal conductivity of SiC nanofluids for heat transfer applicationsLee, Seung Won; Park, Sung Dae; Kang, Sarah, et alARTICLE792 Investigation of viscosity and thermal conductivity of SiC nanofluids for heat transfer applications
2010-12Thermal hydraulic test with 6 MPa nitrogen gas loop for developing the Korean He cooled test blanketLee, Dong Won; Bae, Young Dug; Kim, Suk Kwon, et alARTICLE825 Thermal hydraulic test with 6 MPa nitrogen gas loop for developing the Korean He cooled test blanket
2010-12Experiment and analysis of hypervapotron mock-ups for preparing the 2nd qualification of the ITER blanket first wallLee, Dong Won; Bae, Young Dug; Kim, Suk Kwon, et alARTICLE754 Experiment and analysis of hypervapotron mock-ups for preparing the 2nd qualification of the ITER blanket first wall
2010-10VISCOSITY MEASUREMENTS ON COLLOIDAL DISPERSIONS (NANOFLUIDS) FOR HEAT TRANSFER APPLICATIONSVenerus, David C.; Buongiorno, Jacopo; Christianson, Rebecca, et alARTICLE805 VISCOSITY MEASUREMENTS ON COLLOIDAL DISPERSIONS (NANOFLUIDS) FOR HEAT TRANSFER APPLICATIONS
2010-09Design evaluation of the semi-prototype for the ITER blanket first wall qualificationLee, Dong Won; Bae, Young Dug; Kim, Suk Kwon, et alARTICLE1594 Design evaluation of the semi-prototype for the ITER blanket first wall qualification
2010-07Effects of nanofluids containing graphene/graphene-oxide nanosheets on critical heat fluxPark, Sung Dae; Lee, Seung Won; Kang, Sarah, et alARTICLE985 Effects of nanofluids containing graphene/graphene-oxide nanosheets on critical heat flux
2010-04Thermal-fluid characterizations of zno and sic nanofluids for advanced nuclear power plantsBang, In Cheol; Kim, Ji HyunARTICLE970
2009-11A benchmark study on the thermal conductivity of nanofluidsKim, Ji Hyun; Bang, In Cheol; Buongiorno, Jacopo, et alARTICLE1481 A benchmark study on the thermal conductivity of nanofluids
2009-11AN AXIOMATIC DESIGN APPROACH OF NANOFLUID-ENGINEERED NUCLEAR SAFETY FEATURES FOR GENERATION III plus REACTORSBang, In Cheol; Heo, Gyunyoung; Jeong, Yong Hoon, et alARTICLE723
2009-05Characteristic stability of bare Au-water nanofluids fabricated by pulsed laser ablation in liquidsKim, H.J.; Bang, In Cheol; Onoe, J.ARTICLE853 Characteristic stability of bare Au-water nanofluids fabricated by pulsed laser ablation in liquids
2009-01An axiomatic design approach in development of nanofluid coolantsBang, In Cheol; Heo, GyunyoungARTICLE867 An axiomatic design approach in development of nanofluid coolants
2008-01The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer gridsLee, Kwi Lim; Bang, In Cheol; Chang, Soon HeungARTICLE702 The characteristics and visualization of critical heat flux of R-134a flowing in a vertical annular geometry with spacer grids
2008-01Measurement of Key Pool Boiling Parameters in Nanofluids for Nuclear ApplicationsBang, In Cheol; Buongiorno , Jacopo; Hu, Lin-Wen, et alARTICLE781 Measurement of Key Pool Boiling Parameters in Nanofluids for Nuclear Applications
2007-09Surface wettability change during pool boiling of nanofluids and its effect on critical heat fluxKim, S. J.; Bang, In Cheol; Buongiorno, J., et alARTICLE884 Surface wettability change during pool boiling of nanofluids and its effect on critical heat flux
2007-06Study of pool boiling and critical heat flux enhancement in nanofluidsKim, S. J.; Bang, In Cheol; Buongiomo, J., et alARTICLE1078
2006-10Effects of nanoparticle deposition on surface wettability influencing boiling heat transfer in nanofluidsKim, S. J.; Bang, In Cheol; Buongiorno, J., et alARTICLE678 Effects of nanoparticle deposition on surface wettability influencing boiling heat transfer in nanofluids
2005-12Visualization of a principle mechanism of critical heat flux in pool boilingBang, In Cheol; Chang, SH; Baek, WPARTICLE677 Visualization of a principle mechanism of critical heat flux in pool boiling
2005-07Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubesKim, CH; Bang, In Cheol; Chang, SHARTICLE811 Critical heat flux performance for flow boiling of R-134a in vertical uniformly heated smooth tube and rifled tubes
2005-06Boiling heat transfer performance and phenomena of Al2O3-water nano-fluids from a plain surface in a poolBang, In Cheol; Chang, SHARTICLE873 Boiling heat transfer performance and phenomena of Al2O3-water nano-fluids from a plain surface in a pool
2005-03Direct observation of a liquid film under a vapor environment in a pool boiling using a nanofluidBang, In Cheol; Chang, SH; Baek, WPARTICLE755 Direct observation of a liquid film under a vapor environment in a pool boiling using a nanofluid

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