2023 Conferences
January 4, 2024
Conference
- Ji Yong Kim, Seung Chang Yoo, Joo Hyung Seo, Ji Hyun Kim, In Cheol Bang, Design and Construction of Fluid-to-Fluid Scaled-downed Small Modular Reactor Platform: As a Testbed for the Nuclear-based Hydrogen Production, Proceedings of ICAPP 23, Gyeongju, Republic of Korea, 2023
- Ji Yong Kim, Yunju Lee, Ju Hun Jung, Ji Hyun Kim, In Cheol Bang, Performance Analysis of DISNY Facility: a CRUD Deposition Simulator under PWR Operating Conditions, Transactions of the American Nuclear Society, Indianapolis, USA, 2023
- Ik Jae Jin, In Cheol Bang, Digital Twin and Prediction of Temperature Distribution for Thermosyphon Heat Pipe using LSTM, Transactions of the American Nuclear Society, Indianapolis, USA, 2023
- Ik Jae Jin, In Cheol Bang, The Investigation of Innovative Operation and Maintenance Technology to develop a Road Map for i-SMR, Proceedings of KNS 2023 Spring meeting, Jeju, Republic of Korea, 2023
- Dong Hun Lee, In Cheol Bang, Design and evaluation of a hybrid cesium heat pipe shutdown rod as a passive safety system for microreactors, Proceedings of KNS 2023 Spring meeting, Jeju, Republic of Korea, 2023
- Joo Hyung Seo, In Cheol Bang, Safety Analysis of MicroURANUS LFR for Unprotected Loss of Flow and Unprotected Loss of Heat Sink, Proceedings of KNS 2023 Spring meeting, Jeju, Republic of Korea, 2023
- Ju Hun Jung, In Cheol Bang, Preliminary Analysis of PIUS-type Experimental Apparatus with Hot/Cold Fluids Interface for Inherently Safety, Proceedings of KNS 2023 Spring meeting, Jeju, Republic of Korea, 2023
- Hyun Ji Kim, Ji Yong Kim, In Cheol Bang, Modeling the CRUD Effects on Heat Transfer in Subchannels of Pressurized Water Reactor, Proceedings of KNS 2023 Spring meeting, Jeju, Republic of Korea, 2023
- Do Yong Lim, In Cheol Bang, Preliminary CFD Analysis of Refrigerant Cooled, Scaled Down RPV of OPR1000, Proceedings of KNS 2023 Spring meeting, Jeju, Republic of Korea, 2023
- Do Yong Lim, In Cheol Bang, Scaling Design of Refrigerant-cooled Thermal-Hydraulic Integral Effect Test Facility for OPR1000, 2023 한국유체기계학회 하계학술대회 논문집, Pyeongchang, Republic of Korea, 2023
- Ju Hun Jung, In Cheol Bang, Investigation of Stratification Instability in the Density Lock for Inherent Safety Features of Nuclear Reactors without Control Rod, 2023 한국유체기계학회 하계학술대회 논문집, Pyeongchang, Republic of Korea, 2023
- Ji Yong Kim, Yunju Lee, Ju Hun Jung, Ji Hyun Kim, In Cheol Bang, Feasibility Analysis Study of the DISNY Facility as a test bed for CRUD-related experiment under Pressurized Water Reactor Operating Condition, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Ju Hun Jung, Ji Yong Kim, In Cheol Bang, Instability at the Interface between Hot/Cold Fluids in the Density Lock using Numerical Analysis for Inherently Safe Reactor, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Joo Hyung Seo, Ji Yong Kim, In Cheol Bang, Analysis of Flow Blockage for the Fuel Assembly in Lead-cooled Fast Reactor and Comparison of Analysis According to the Changed Assembly Design, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Ik Jae Jin, In Cheol Bang, Deep learning based thermal performance optimization for the liquid metal heat pipe, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Dong Hun Lee, In Cheol Bang, Investigation of Hybrid Heat Pipe Shutdown Rod Concept of Microreactor as a Passive Safety System, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Hyeon Ji Kim, Ji Yong Kim, In Cheol Bang, Simulation of the CRUD Effect in Subcooled Nucleate boiling area in the Subchannels of the 7×7 Nuclear Fuel Assembly, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Ye Yeong Park, In Cheol Bang, Performance Analysis of Water Heat Pipe for Application of the Passive Cooling System in Nuclear Power Plants, Proceedings of NURETH-20, Wasington DC, USA, 2023
- Ju Hun Jung, In Cheol Bang, Preliminary Analysis of SMR-DAC Integration System for Carbon Dioxide Removal Approach, Proceedings of KNS 2023 Autumn meeting, Gyeongju, Republic of Korea, 2023
- Do Yeong Lim, In Cheol Bang, Preliminary MARS-KS Analysis of OPR1000’s Scaled Thermal-Hydraulic Facility, URILO-II, Proceedings of KNS 2023 Autumn meeting, Gyeongju, Republic of Korea, 2023
- Ji Yong Kim, Yunju Lee, Byeongju Kim, Ji Hyun Kim, In Cheol Bang, Experimental Investigation of the Fouling Characteristics of the CRUD on Pressurized Water Reactor Operating Conditions, Proceedings of KNS 2023 Autumn meeting, Gyeongju, Republic of Korea, 2023
- Joo Hyung Seo, In Cheol Bang, Analysis of Heat Loss in Dual Vessel Design of Low Temperature SMR, Proceedings of KNS 2023 Autumn meeting, Gyeongju, Republic of Korea, 2023
- Ik Jae Jin, In Cheol Bang, Experimental Investigation of Impact of Sodium Heat Pipe Geyser Boiling on Microreactor, Proceedings of KNS 2023 Autumn meeting, Gyeongju, Republic of Korea, 2023
- Do Yeong Lim, In Cheol Bang, Design of Reduced Integral Effect Test Facility of OPR1000 And Preliminary Analysis using MARS-KS, Proceedings of WORTH-10, Jeju, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, The Conceptual Heat Exchanger Design for Heat Pipe Cooled Micro Reactor, Proceedings of KNS 2023 spring meeting, Jeju, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, Preliminary Passive Safety Valve Design for Heat Exchanger of Micro Reactor, Poster presentation, Ulsan, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, The Preliminary Design for Heat Exchanger in Heat Pipe Cooled Micro Reactors by Considering Heat Pipe Failure Scenarios, Abstract, Busan, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, A Study on Thermoelectric Hybrid Heat Exchanger Concept for Heat Pipe Cooled Micro Reactors, Proceedings of KNS 2023 spring meeting, Gyeongju, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, Performance Assessment for a Hybrid Heat Exchanger Concept of Heat Pipe Cooled Reactor: Combining Thermoelectric Generators and an Open-Air Brayton Cycle, Poster Presentation, Jeju, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, Efficiency Evaluation of Hybrid Heat Exchanger: Integrating Thermoelectric Generators with an Open-Air Brayton Cycle in Heat Pipe Cooled Reactors, Proceedings of WORTH-10 2023 meeting, Jeju, Republic of Korea, 2023
- Faruk Celik, In Cheol Bang, Initial Study on The Effect of Neutron Activation of Lithium Cooled Heat Pipe: Performance and Safety Evaluation, Proceedings of WORTH-10 2023 meeting, Jeju, Republic of Korea, 2023
2023 Journals
January 4, 2024
Journals
- Ik Jae Jin, Do Yeong Lim, In Cheol Bang, Deep-learning-based system-scale diagnosis of a nuclear power plant with multiple infrared cameras, Nuclear Engineering and Technology, Vol. 55, 493-505, 2023
- Ik Jae Jin, Do Yeong Lim, In Cheol Bang, Development of fault diagnosis for nuclear power plant using deep learning and infrared sensor equipped UAV, Annals of Nuclear Energy, Vol. 181, 109577, 2023
- Min Ho Lee, Dong Wook Jerng, In Cheol Bang, Effects of decay heat and cooling condition on the reactor pool natural circulation under RVACS operation in a water 2-D slab model, Nuclear Engineering and Technology, Vol. 55, 1821-1829, 2023
- Ji Yong Kim, Yunju Lee, Ji Hyun Kim, In Cheol Bang, The DISNY facility for sub-cooled flow boiling performance analysis of CRUD deposited zirconium alloy cladding under pressurized water reactor condition: Design, construction, and operation, Nuclear Engineering and Technology, Vol. 55, 3164-3182, 2023
- Dong Hun Lee, In Cheol Bang, Experimental investigation of heat transfer limitations in concentric annular sodium heat pipes and thermosyphon, Applied Thermal Engineering, Vol. 232, 121020, 2023
- Dong Hun Lee, In Cheol Bang, Experimental Investigation of Thermal Behavior of Overfilled Sodium Heat Pipe, International Journal of Heat and Mass Transfer, Vol.215, 124449, 2023
- Ye Yeong Park, In Cheol Bang, Experimental Study on 3D Printed Heat Pipes with Hybrid Screen–Groove Combined Capillary Wick Structure, Applied Thermal Engineering, Vol. 232, 121037, 2023
- Ji Yong Kim, Ye Yeong Park, In Cheol Bang, Performance analysis of heat pipe-based passive in-core decay heat removal system for the small modular reactor design with MARS-KS code, Annals of Nuclear Energy, Vol. 194, 110091, 2023
- Do Yeong Lim, Ik Jae Jin, In Cheol Bang, Heat-Vision Based Drone Surveillance Augmented by Deep Learning for Critical Industrial Monitoring, Scientific Reports, Vol. 13, 22291, 2023
2022 Conferences
June 5, 2023
Conference
- Do Yeong Lim, Ik Jae Jin, In Cheol Bang, Convolutional Neural Network-based Boiling Regime Determination Using Acoustic Emission Signal Image, Proceedings of NURETH-19, Virtual conference, 2022
- Dong Hun Lee, In Cheol Bang, Cooling Performance Enhancement of the Dry Storage Cask Using Hybrid Heat Pipe, Proceedings of NURETH-19, Virtual conference, 2022
- Ye Yeong Park, In Cheol Bang, Performance Analysis of 3D-printed Heat Pipe Wick Design for Space Nuclear Reactor Application, Proceedings of NURETH-19, Virtual conference, 2022
- Ye Yeong Park, Chan soo Kim, In Cheol Bang, Preliminary Performance Evaluation of Radiator Heat Pipe for Space Nuclear Reactor Application, Proceedings of NETS-2022, Cleveland, USA, 2022
- Ji Yong Kim, Hyeon Ji Kim, In Cheol Bang, Design Study of CRUD Thermal Properties Characterization Facility DISNY under Pressurized Water Reactor Normal Operating Condition, Proceedings of ATH-2022, Anaheim, USA, 2022
- Ik Jae Jin, Do Yeong Lim, In Cheol Bang, Deep Learning Based System Diagnosis for Nuclear Power Plant Using Infrared Thermal Cameras, Proceedings of ATH-2022, Anaheim, USA, 2022
- Min Ho Lee, In Cheol Bang, Dong Wook Jerng, Integrated Experiments for RVACS Using Combination of Two Different Similarity Law, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Do Yeong Lim, In Cheol Bang, Feasibility Study of Deep Learning and Acoustic Vibration-based Two-phase Monitoring Technology on Nuclear Reactor, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Ji Yong Kim, Ye Yeong Park, In Cheol Bang, Investigation of the Heat Removal Capability of the Hybrid Control Rod in Natural Circulation-type SMR under Station Black Out Accident with MARS-KS code, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Ju Hun Jeong, Ji Yong Kim, In Cheol Bang, Investigation of Natural Circulation Instability for Inclined One-loop with Single-phase in MARS-KS, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Hyeon Ji Kim, Do Yeong Lim, In Cheol Bang, Feasibility Study of Hybrid Heat Pipe Control Rod Application on Nuclear Power Plant using UNIST Reactor Innovation LOop(URI-LO), Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Ye Yeong Park, In Cheol Bang, Design of Heat Pipe Radiator for Thermal Management System in Space Nuclear Reactor, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Joo hyung Seo, In Cheol Bang, System Analysis of Flow Blockage Phenomena in a Liquid Metal-cooled Small Marine Reactor, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Ji Yong Kim, Yunju Lee, Junhyuk Ham, Ji Hyun Kim, In Cheol Bang, Establishment of Experimental Facility to Investigate the Sub-cooled Boiling Heat Transfer Characteristics of Fouled Cladding Surface at PWR Conditions, Proceedings of KSFM 2022 Summer meeting, Pyeongchang, Korea, 2022
- Dong Hun Lee, In Choel Bang, Thermal Performance Investigation of Liquid Metal Heat Pipe Using 3D Printing Technology for Advanced Microreactor, Proceedings of KSFM 2022 Summer meeting, Pyeongchang, Korea, 2022
- Ji Yong Kim, Yunju Lee, Junhyuk Ham, Ji Hyun Kim, In Cheol Bang, 가압 경수형 원전환경 크러드 침적 모사 실험 장치 구축 및 예비 성능 평가, Proceedings of KJHM 2022 Summer meeting, Busan, Korea, 2022
- Ik Jae Jin, In Cheol Bang, Preliminary Study of IR Sensor Equipped Drone-based Nuclear Power Plant Diagnosis Method Using Deep Learning, Proceedings of KNS 2022 Spring meeting, Jeju, Korea, 2022
- Ik Jae Jin, Do Yeong Lim, In Cheol Bang, IR based Multi-Components Diagnosis for Nuclear Power Plant using Deep Learning, Proceedings of KSFM 2022 Summer meeting, Pyeongchang, Korea, 2022
- Ik Jae Jin, Do Yeong Lim, In Cheol Bang, 적외선 열화상 및 딥러닝 기반의 원자력 발전소 진단 기술 개발, Proceedings of KJHM 2022 Summer meeting, Busan, Korea, 2022
- Do Yeong Lim, In Cheol Bang, Ultrasound Vibrational Characteristics of Nucleate Boiling Bubble, Proceedings of NUTHOS-13, Virtual conference, 2022
- Ye Yeong Park, In Cheol Bang, Analysis of the Bending Effect of Heat Pipe for Nuclear Reactor Application, Proceedings of NUTHOS-13, Virtual conference, 2022
- Joo hyung Seo, In Cheol Bang, Flow Blockage Analysis of the Fuel Assembly in a Conceptual Micro-marine Liquid Metal-cooled Fast Reactor, Proceedings of NUTHOS-13, Virtual conference, 2022
- Do Yeong Lim, In Cheol Bang, Fluid-to-Fluid Scaling Design for Integral Effect Test Facility of OPR1000 Using R134a, Proceedings of the KNS 2022 Autumn Meeting, Changwon, Korea, 2022
- Ye Yeong Park, In Cheol Bang, Preliminary Experiments of Large-scale Water Heat pipe as Passive Cooling System in Nuclear Power Plants, Proceedings of the KNS 2022 Autumn Meeting, Changwon, Korea, 2022
- Joo hyung Seo, In Cheol Bang, Inverted Core Flow Blockage Analysis in Micro-Marine Lead Cooled Fast Reactor, Proceedings of the KNS 2022 Autumn Meeting, Changwon, Korea, 2022
- Ji Yong Kim, Yunju Lee, Ji Hyun Kim, In Cheol Bang, Investigation of Pool Boiling Heat Transfer Characteristic of CRUD Deposited Zirconium Alloy Cladding, Proceedings of NTHAS-12, Miyazaki, Japan, 2022
- Do Yeong Lim, In Cheol Bang, Preliminary Design of Scaled-down Thermal Hydraulic Integral Test Facility of OPR1000, Proceedings of NTHAS-12, Miyazaki, Japan, 2022
- Ye Yeong Park, In Cheol Bang, Experimental Study of Metal Additive Manufactured Heat Pipe with Screen-groove Combined Wick Structure, Proceedings of NTHAS-12, Miyazaki, Japan, 2022
- Joo hyung Seo, In Cheol Bang, A Sensitivity Analysis of Flow Blockage Phenomena with CFD in Conceptually Designed Micro-Marine LFR, Proceedings of NTHAS-12, Miyazaki, Japan, 2022
- Do Yeong Lim, In Cheol Bang, Fluid-to-Fluid Scaling Analysis and Design for Reduced Integral Effect Test Facility of OPR 1000, Transactions of the ANS 2022 Winter Meeting, Phoenix, USA, 2022
- Do Yeong Lim, In Cheol Bang, 원자로 내 비등현상 모니터링을 위한 음향진동 및 딥러닝 적용 연구, Proceedings of KSFM 2022 Winter meeting, Jeju, Korea, 2022
- Ji Yong Kim, In Cheol Bang, 소형 모듈 원자로 요소 기술 적용 및 평가를 위한 혁신 플랫폼 설계 연구, Proceedings of KSFM 2022 Winter meeting, Jeju, Korea, 2022
- Ik Jae Jin, In Cheol Bang, Development of the Nuclear Power Plant Diagnosis Technique based on Deep Learning with Infrared Camera embedded Drone, Proceedings of NUTHOS-13, Virtual conference, 2022
2021 Journals
April 7, 2022
Journals
- Seok Bin Seo, In Cheol Bang*, Hisashi Ninokata, Antonio Cammi, Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system, Nuclear Engineering and Design, Vol. 381, 111349, 2021
- Min Ho Lee, Dong Wook Jerng, In Cheol Bang*, Study on blockage after downward discharge of the molten metallic fuel with radiographic visualization, Nuclear Engineering and Technology, Vol. 54 (1), 117-129, 2021
2020 Conferences
January 5, 2020
Conference
- Do Yeong Lim, In Cheol Bang, Artificial Intelligence-based Phase-Change Regime Classification of Acoustic Emission Detection in Pool Boiling, Transactions of the American Nuclear Society, Virtual conference, 2020
- Kyung Mo Kim, In Cheol Bang, Micro-Integral Effect Test of URI-Lo with Infrared Imaging Technique of Drone, Proceedings of KNS 2020 Spring meeting, Virtual conference, 2020
- Min Ho Lee, Dong Wook Jerng, In Cheol Bang, Design of the experimental facility for the RVACS natural circulation of the PGSFR, SINCRO-3D, Proceedings of KNS 2020 Spring meeting, Virtual conference, 2020
- Do Yeong Lim, Ji Yong Kim, Dong Hun Lee, Kyung Mo Kim, In Cheol Bang, Identifying Heat Transfer Regimes by Acoustic Analysis in Pool and Flow Boiling, Proceedings of KNS 2020 Spring meeting, Virtual conference, 2020
- Dong Hun Lee, In Cheol Bang, Study about the impact of Pr effect on the validity of Boussinesq approximation in molten salt natural circulation, Proceedings of KNS 2020 Spring meeting, Virtual Conference, 2020
- Ye Yeong Park, In Cheol Bang, Study of diameter variation affecting the thermal performance of heat pipe for space nuclear reactor applications, Proceedings of KNS 2020 Spring meeting, Virtual Conference, 2020
- Ji Yong Kim, Kyung Mo Kim, In Cheol Bang, Effect of CVD grown graphene monolayer thermal effusivity on phase change heat transfer in 2-D plate condition with Highly Wettable FC-72, Proceedings of IEEE-19, Virtual conference, 2020
- Dong Hun Lee, In Cheol Bang, Numerical study for investigating the validity of Boussinesq approximation of molten salt natural and mixed convection with internal heat source, Proceedings of the 11th National Congress on Fluids Engineering, Jeju, Korea, 2020
- Dong Hun Lee, In Cheol Bang, Investigating the validity of the Boussinesq approximation on natural circulation of molten salt with internal heat source using OpenFOAM, Transactions of the ANS 2020 Winter Meeting, Virtual conference, 2020
- Ye Yeong Park, In Cheol Bang, Preliminary design optimization study of heat pipe for space reactor application, Transactions of the ANS 2020 Winter Meeting, Virtual conference, 2020
- Do Yeong Lim, In Cheol Bang, Deep Learning and Acoustic Signal-based Pool Boiling Monitoring System, Proceedings of KNS 2020 Autumn meeting, Virtual conference, 2020
- Ji Yong Kim, Tung Dong Cao Nguyen, Deokjung Lee, In Cheol Bang, Preliminary Safety Analysis Results of Lead Cooled Fast Reactor Design using MARS Code, Proceedings of KNS 2020 Autumn meeting, Virtual conference, 2020
- Kyung Mo Kim, In Cheol Bang, Decay Heat Removal Characteristics of Full-Scale Hybrid Control Rod-Heat Pipe for Advanced Spent Fuel Dry Storage Cask Design, Proceedings of KNS 2020 Autumn meeting, Virtual conference, 2020
- Ye Yeong Park, Kyung Mo Kim, In Cheol Bang, Performance Analysis of Heat Pipe Design for Space Nuclear Reactor Application, Proceedings of KNS 2020 Autumn meeting, Virtual conference, 2020
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