Faculty Research Profile
In Cheol Bang
학력
· 2004: Ph. D. Nuclear & Quantum Engineering, KAIST, Rep. of Korea
· 2000: M. S. Nuclear & Quantum Engineering, KAIST, Rep. of Korea
· 1998: B. S. Nuclear & Quantum Engineering, KAIST, Rep. of Korea
주요 경력
· 2020~present: Head of Department of Nuclear Engineering, UNIST
· 2019~2020: Visiting Professor, University of California San Diego
· 2018~present: Professor, UNIST
· 2016~2019: Dean of Budget and Planning, UNIST
· 2013~2017: Associate Professor, UNIST
· 2009~2012: Assistant Professor, UNIST
· 2007~2009: Assistant Professor, Tokyo Institute of Technology, Japan
· 2005~2007: Postdoc. MIT, USA
· 2004~2005: Postdoc. KAIST, Rep. of Korea
수상/학회/외부활동
· 2019: Academic Excellence Prize at 2019 Korean Nuclear Society
· 2009~Present: Marquis Who’s Who in the World
· 2008: Atomic Energy Society of Japan
· 2006~Present: American Nuclear Society
· 2006: User of High Temperature Materials Lab in Oak Ridge National Laboratory (USA, 2006)
· 2006: User of Center for Nanoscale System in Harvard University (USA, 2006)
· 2002~2005: one of the most cited paper, Int. J of Heat and Mass Transfer, Elsevier.
· 1998~Present: Member of Korean Nuclear Society
원자력 열수력 및 안전 실험실
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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).
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).
연구분야
Nuclear System Design and Analysis for Nuclear Safety, Development of CHF and Boiling Enhancement technology, Nano-engineered Fluids & Surfaces
Nuclear System Design and Analysis for Nuclear Safety, Development of CHF and Boiling Enhancement technology, Nano-engineered Fluids & Surfaces
연구주제
· 원자력 안전을 위한 원자력 시스템 설계 및 분석 (첨단대형원전, 혁신소형모듈형원전)
Nuclear System Design and Analysis for Nuclear Safety
· CHF 및 Boiling Enhancement 기술
Development of CHF and Boiling Enhancement technology
· 나노 공학 유체 및 표면 융합 냉각재 및 히트파이프 기술
Nano-engineered Fluids & Surfaces combined Coolant and Heat Pipe Technology
· 인공지능, 적외선, 음향 융합 스마트 센싱 기술
Artificial Intelligence (AI) – IR – AE hybrid smart sensing
Nuclear System Design and Analysis for Nuclear Safety
Development of CHF and Boiling Enhancement technology
Nano-engineered Fluids & Surfaces combined Coolant and Heat Pipe Technology
Artificial Intelligence (AI) – IR – AE hybrid smart sensing
국가연구개발사업 기술 분류체계
국가과학기술표준분류
EF. 에너지/자원 > EF99. 기타 에너지자원 > EF9999. 달리 분류되지 않는 에너지/자원
논문
· Nuclear Engineering and Design / Design and Operation of the Transparent Integral Effect Test Facility, URO-LO for Nuclear Innovation Platform / Kyung Mo Kim, In Cheol Bang / 2020-08
· INTERNATIONAL JOURNAL OF ENERGY RESEARCH / Adjoint-based sensitivity analysis of circulating liquid fuel system for the multiphysics model of molten salt reactor / eong, Yeong Shin; Cervi, Eric; Cammi, Antonio; Ninokata, Hisashi; Bang, In Cheol / 2020-04
· APPLIED PHYSICS LETTERS / Effects of nanofluids containing graphene/graphene-oxide nanosheets on critical heat flux / Park, Sung Dae; Lee, Seung Won; Kang, Sarah; Bang, In Cheol; Kim, Ji Hyun; Shin, Hyeon Suk; Lee, Dong Wook; Lee, Dong Won / 2010-07
특허
· [국내] Rotating mixing vane attached to nuclear fuel rod spacer grid / patent no. 10-0456500