Conference papers/Posters/Reports


2021. Hyuntaek Rho and Youho Lee. Development of an Advanced Cladding Mechanical Model and Its Application for Thermal Hydraulics Coupled Failure Analysis of SiC LWR Fuel Cladding during LBLOCA .Transactions of the Korean Nuclear Society Fall Meeting.  

2021. Sangbum Kim, Kyunghwan Keum, Youho Lee, Il soon Hwang, Han-Chil Lee. PILLAR: Pool-type Integral Leading facility for Lead-alloy cooled Advanced small modular Reactor, and Its Use for Natural Convection Study and Corrosion. TMS Annual Meeting & Exhibition.

2020. Kyunghwan Keum, Youho Lee. Mechanical Behavior of Hydrogen charged Zircaloy-4 at Elevated Temperatures. NUMAT 2020, Ghent Belgium.

2020. Hyuntaek Rho, Youho Lee. Development of an advanced cladding mechanical model for SiC cladding failure mode during LBLOCA with thermal hydraulics coupled simulation. NUMAT 2020, Ghent Belgium.

2020. Sangbum Kim, Youho Lee. Investigation of Hydrogen induced Cladding Embrittlement in Spent Fuel Pool Environment. Transactions of the Korean Radioactive Waste Society Spring Meeting, Gunsan, Korea, July 29-31.

2020. Youho Lee, Kyunghwan Keum, Hyunwoo Yook, Dongju Kim, Jaeyoung Choi, Kyoung-Jae Chung. Advanced Ductility Assessment for High-Burnup Zirconium-based Alloy Cladding. Symposium on Zirconium cladding development status, Korean Institute of metals and materials, Spring meeting, virtual conference, July. 15- 17.

2020. Hyunwoo Yook, Kyunghwan Keum, Dongju Kim, Youho Lee. Effect of Non-Isothermal Transient Zircaloy Oxidation on Emergency Core Cooling System Criteria. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, July 9-10.

2020. Kyunghwan Keum, Hyunwoo Yook, Dongju Kim, Youho Lee. The Effect of Cooling Rates on the Post-LOCA Ductility of Zircaloy Cladding. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, July 9-10.

2020. Dongju Kim, Kyunghwan Keum, Hyunwoo Yook, Youho Lee. Development and Validation of a Code for the Oxygen Distribution of Zircaloy Cladding in Non-Isothermal Transient Steam oxidation. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, July 9-10.

2020. Gyujae Nam, Youho Lee. Comparison for Spent Fuel Behavior of PWR and SMRs. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, July 9-10.


2020. Osman Anderoglu, Cemal Cakez, Shuprio Ghosh, Khaled Talaat, Sang Lee, Youho Lee, Keith Woloshun, Seung Kim, Stuart Maloy, Cetin Unal, Michael Ickes, Paolo Ferroni. Establishment of a Lead Loop Facility to Support Lead Cooled Fast Reactor Design. 2020 TMS Annual Meeting & Exhibition, Coatings and Surface Engineering for Environmental Protection II

2019. Osman Anderoglu, Cemal Cakez, Shuprio Ghosh, Brian Romero, Khaled Talaat, Sang Lee, Youho Lee, Keith Woloshun, Seung Jun Kim, Stuart Maloy, Cetin Unal , Michael Ickes, Paolo Ferroni. Establishment of an Out-of-Pile Lead Loop Facility to Support Lead Cooled Fast Reactor Design. Transaction of ANS’19 Winter Meeting.

2019. Khaled Talaat, Sang Lee, Youho Lee, Osman Anderoglu, Cemal Cakez, Shuprio Ghosh , Keith Woloshun, Seung Jun Kim, Stuart Maloy, Cetin Unal, Michael Ickes, Paolo Ferroni. Numerical Investigation of Molten Lead Flow in a Closed Loop to Estimate Pressure Demand. Transaction of ANS’19 Winter Meeting.

2019. Khaled Talaat, Rubel Das, Brian Romero, Cemal Cakez, Osman Anderoglu, Sang Lee, Youho Lee, Heng Ban, Keith Woloshun, Seung Jun Kim, Dasari Rao, Cetin Unal. Development of a Numerical Framework to Model Flow Accelerated Corrosion in a Lead Loop. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18).

2019. Soon Kyu Lee , Nicholas R. Brown, Kurt A. Terrani, Colby B. Jensen, Heng Ban, Youho Lee. Study of Transient CHF and Post-CHF Flow Boiling. 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-18).

2019. Soon Kyu Lee, Nicholas R. Brown, Kurt A. Terrani, Youho Lee. Steady-State Flow CHFs with Various Tube Materials. 18th International Topical Meeting onNuclear Reactor Thermal Hydraulics (NURETH-18).

2018. Divya Prakash, Youho Lee. Development of Superior Thermal Shock Tolerant Material for Nuclear Components by Engineering Surface Heat Transfer Modes. Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. Mingfu He, Youho Lee. Comparative Analyses of CHF Prediction Performance between Deep Learning and Physics Approaches to Pool Boiling Enhanced by Microstructure. Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. Soon Lee, Maolong Liu, Edward Blandford, Youho Lee, Nicholas Brown, Heng Bang, Colby Jensen, Kurt Terrani . Comparison of Steady-State and Transient Condition Flow Boiling Critical Heat Flux (CHF) of FeCrAl Alloy, Zircaloy-4 and Inconel600. Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. Seong Gu Kim, Maolong Liu, Youho Lee. Heat Transfer Distribution of Randomly Packed Pebble-Bed Fuels for Fluoride Salt-Cooled High Temperature Reactor (FHR). Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. Dongjune Chang, Youho Lee. Preliminary Experiments of Wireless Advanced Instrumentation Toward Packed Pebble Heat Transfer. Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. Amir Ali, Edward Blandford, Youho Lee, Khalid Hattar, Hyun-Gil Kim, Dongjune Park. Surface Wettability Measurements and Pool Boiling CHF Prediction of Ion Irradiated Coated Zircaloy. Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. Dongjune Chang, Maolong Liu, Youho Lee. Analysis of Transient Flow Change Aided by a Support Vector Machine Method. Transaction of ANS’18 Winter Embedded Topical Meeting: Advances in Thermal Hydraulics (ATH 2018).

2018. David Weitzel, Youho Lee, Amir Ali, Michael Short, Govindarajan Muralidrahan. Numerical Model of FLiBe Corrosion of Bimetallic alloy. Transaction of ANS’18 Winter Meeting.

2018. Malong Liu, Jared Thurgood, Youho Lee, Dasari Rao. Development of Effective Thermal Conductivity Model for FCM and Pebble Fuels with Randomly Distributed TRISO Particles. Oral Presentation NUMAT 2018.

2018. Divya Prakash, Youho Lee. Development of Thermal Shock Tolerant Material with Surface Modification. Poster Presentation NUMAT 2018.

2018. Malong Liu, Satbyoul Jung, Hyungdae Kim, Youho Lee. Nucleate Boiling Induced Thermal Stress. Poster Presentation NUMAT 2018.

2018. Soon Lee, Maolong Liu, Nicholas Brown, Kurt Terrani, Youho Lee. Comparison of Flow Critical Heat Flux (CHF) among FeCrAl alloy, Zircaloy, and Inconel, and its Implications on Nuclear Fuel Design and Accident Progression. Poster Presentation NUMAT 2018.

2018. David Weitzel, Youho Lee, Michael Short, Mike Laufer, Sam Sham. Experiment on Compatibility of Single and Bimetallic Alloys in a Subscale Flowing FLiBe Loop. Transaction of ICAPP' 2018.

2017. Youho Lee, Edward Blandford, Nicholas Brown, Amir Ali, Maolong Liu, Wade Marcum, Daniel LaBrier, Simon Walker, Geoffrey Hewitt, Raad Issa, Colby Jensen, John Strumpell, Raul Rebak. A NEUP Example of US-UK Collaboration: An Experimental and Analytical Investigation into Critical Heat Flux Implications for Accident Tolerant Fuel Concepts. Transaction of ANS’17 Winter Meeting.  

2016. Youho Lee, Bokyung Kim, Hee Cheon NO Rethinking of Zircaloy Embrittlement Criteria for Improving Safety Margin of Light Water Reactor. Transaction of ANS’16 Winter Meeting.  November 6-10, 2016 Caesars PalaceLas Vegas, NV.

2016. Youho Lee, Bokyung Kim, Hee Cheon NO. Rethinking the Zircaloy Embrittlement Criteria and Its Impact on the Safety Margin. Transactions of the Korean Nuclear Society Spring Meeting. Jeju , Korea, May 11-13.

2016. Youho Lee. Mechanical behavior of SiC clad LWR fuels for steady-states and LOCA. ICAPP'2016, Kazimi’s Special Session І, USA, April 17-20.

2015. Youho Lee, Seong min Son, and Jeong Ik Lee. A double-wall LWR cladding concept with multi-cylinder misfitting. TOPFUEL. Zurich, Switzerland, September 13-17.

2015. Youho Lee, and Hee Cheon NO. Heat Transfer Origin of Thermal Shock fracture and its Application to LWR Fuel during Reflood. NURETH-16. Chicago, U.S.A, August 30- September 4.


2015. Youho Lee, Hee Cheon NO, and Jeong Ik Lee. Design Optimization of Multi-Layer Silicon Carbide Cladding for Light Water Reactors. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, May 7-8.

2015. Youho Lee, Jeong Ik Lee, and Hee Cheon NO. Effects of Heat Transfer Coefficient Treatments on Thermal Shock Fracture Prediction for LWR Fuel Claddings in Water Quenching. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, May 7-8.

2015. Faris B. Sweidan, Youho Lee, and Ho Jin Ryu. The Effect of Protective Coating on the LOCA Simulation of Zircaloy-4 Cladding. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, May 7-8.

2014. Min-Gil Kim, Youho Lee, and Jeong Ik Lee. Flow Regime Comparison of MARS-KS to SPACE during LBLOCA. Transactions of the Korean Nuclear Society Autumn Meeting. Pyeongchang, Korea, October 30-31.

2014. H.J. Kim, S.J. Wang, S.W. Seon, Y. Lee, B.H. Park, S.W. Yoon. Thermal Analysis on the KSTAR ICRF Vacuum Feedthrough using ANSYS. Transactions of the Korean Nuclear Society Autumn Meeting. Pyeongchang, Korea, October 30-31.

2014. Min-Gil Kim, Youho Lee, and Jeong Ik Lee. Preliminary Comparisons of Thermal Hydraulic Characteristics of Core Using from 10 by 10 Fuel Assembly to 20 by 20 Fuel Assembly for SMART. Transactions of the Korean Nuclear Society Autumn Meeting. Pyeongchang, Korea, October 30-31.

2014. Youho Lee, Hee Cheon No, and Jeong Ik Lee. Structural Analysis of Surface-Modified Oxidation-Resistant Zirconium Alloy Cladding for Light Water Reactors. Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, May 29-30.

2014. Min-Gil Kim, Youho Lee, and Jeong Ik Lee. Preliminary Comparisons of Thermal Hydraulic Characteristics of Core Using from 10 by 10 Fuel Assembly to 20 by 20 Fuel Assembly for SMART . Transactions of the Korean Nuclear Society Spring Meeting. Jeju, Korea, May 29-30.

2014. Youho Lee, Ho Sik Kim, and Hee Cheon NO. Safety of Silicon Carbide Cladding for Fail-Safe Simple Economical SMR (FASES). Summary of ANS’14, Embedded Topical Meeting on Nuclear Fuels & Structural Materials for Next Generation Nuclear Reactors. 9887. Reno, NV, USA, June 15-19.

2014. Youho Lee, Thomas J. McKrell, and Mujid S. Kazimi. Key Structural Challenges of SiC as Fuel Cladding for LWRs. Proceedings of ICAPP’14. 14358. Charlotte, NC, USA, April 6-9.

2014. Youho Lee, and Jeong Ik Lee. Structural Assessment of Intermediate Printed Circuit Heat Exchanger for Supercritical CO2 Cycle attached to Sodium Fast Reactor. Proceedings of ICAPP’14. 14340. Charlotte, NC, USA, April 6-9.

2014. Min-Gil Kim, Youho Lee, and Jeong Ik Lee. Comparison of Thermal Hydraulic Performance of Rod-Type Fuel for Small Modular Reactor Application. Proceedings of ICAPP’14. 14067. Charlotte, NC, USA, April 6-9.

2013. Youho Lee, Thomas J. McKrell, and Mujid S. Kazimi. Thermal Shock Fracture of Silicon Carbide and Its Application to LWR Fuel Cladding Performance During Reflood. Proceedings of ICAPP’13. 101.13. Jeju Island, Korea, April 14-18.

2012. Youho Lee, Chao Yue, Ramsey P. Arnold, Thomas J. McKrell, and Mujid S. Kazimi. Oxidation of SiC Cladding Under Loss of Coolant Accident (LOCA) Conditions in LWRs. Proceedings of ICAPP’12. 12265. Chicago, USA, June 24-28.

2012. C. W. Forsberg, Y. Lee, M. Kulhanek, and M. J Driscoll. Gigawatt-Year Nuclear Geothermal Energy Storage for Light-Water and High-Temperature Reactors. Proceedings of ICAPP’12. 12446.  Chicago, USA, June 24-28.

2012. Koroush Shirvan, Yu-ChihKo, Youho Lee, Sheng Xu, YaninSukjai, and Mujid S. Kazimi. Advanced Compact Nuclear Reactors. MIT Energy Show Case ’12. Poster. Boston, USA, March 16.

2011. Youho Lee, Charles W. Forsberg, and M. J Driscoll. Conceptual Design of Nuclear-Geothermal Energy Storage Systems for Variable Electricity Production. Summary of ANS’11 Winter Meeting. 4548. Washington, D.C., USA, October 30- November 3.

2011. Charles W. Forsberg, Rebecca Krentz-Wee, You Ho Lee, and Isaiah O. Oloyede. Nuclear Energy for Low-Carbon Heavy-Oil Recovery and Gigawatt-Year Heat Storage for Peak Electricity Production. MIT Center for Advanced Nuclear Energy Systems.Report.MIT-NES-TR-011. Cambridge, USA.

2011. J Stempien, R. Arnold, Y. Lee, C. Yue, J. Dobesisky, D. Carpenter, G. Kohse, T. McKrell, E. Pilat, and  M. Kazimi. Advanced Fuels for Enhanced Safety and Economics of Nuclear Energy. MIT Energy Night’11. Poster. Cambridge, USA, October 21.

2011. Youho Lee. et.al. Conceptual Design of Molten Salt Loop Experiment for MIT Research Reactor. MIT Center for Advanced Nuclear Energy Systems. Report.MIT-MRR-DES-00. Cambridge, USA.

2010. Youho Lee, Isaiah Oloyede, Charles W. Forsberg, and Michael J. Driscoll. Requirements for Seasonal Electricity Storage. MIT Energy Night’10. Poster. Cambridge, USA, October 22.

2010.You Ho Lee, Charles W. Forsberg, Michael J. Driscoll, and Benyamin Sapiie. Options for Nuclear Gigawatt-Year Peak Electricity Storage Systems. Proceedings of ICAPP’10. 10212. San Diego, USA, June 13-17.

2007. You Ho Lee, and Hee Cheon NO. Computational Analysis of a Direct Thermo-Chemical Sulfuric Acid Decomposer Used for Hydrogen Production. Transactions of the Korean Nuclear Society Meeting’ 07. Jeju, Korea, May 10-11.