Conference

1. 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
2. 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
3. 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
4. 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
5. 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
6. 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
7. 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
8. 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
9. 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
10. 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
11. 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
12. 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
13. 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
14. 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
15. 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
16. 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
17. 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
18. 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
19. 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
20. 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
21. 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
22. 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
23. 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
24. 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
25. 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
26. Faruk Celik, In Cheol Bang, Preliminary Passive Safety Valve Design for Heat Exchanger of Micro Reactor, Poster presentation, Ulsan, Republic of Korea, 2023
27. 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
28. 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
29. 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
30. 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
31. 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