S.Y. Kim and S.H.Lee "Evaluation of Optimization Algorithms for Fracture Parameter Calibration in Spent Nuclear Fuel Cladding with Reoriented Hydrides" KNS spring meeting, Jeju, Korea, 2025. 05

G.H. Jeong and S. H. Lee "Calculating Radionuclide Release Rates from Deep-sea Submerged Spent Fuel Casks: a Surrogate Model Approach" KNS spring meeting, Jeju, Korea, 2025. 05

D.I. Park, H.R. Lee and S.H. Lee "Safety Evaluation of HIC based on the Type A Transport Requirement" KNS spring meeting, Jeju, Korea, 2025. 05

S.Y. Kim and S. H. Lee "A Multi-Objective Approach to Identify Fracture Parameters of Spent Nuclear Fuel Cladding with Reoriented Hydrides" WCSMO2025, Kobe, Japan, 2025. 05

S.Y. Kim and S.H. Lee "Fracture Parameter Estimation Using Multi-Objective Optimization Considering Hydride Morphology Variation in Spent Nuclear Fuel Cladding" KRS spring meeting, Busan, Korea, 2025.05

G.H. Jeong and S.H. Lee "Simulation of Bending Behavior of High-Burnup SNF Rods With Interfacial Bond Failure" KRS spring meeting, Busan, Korea, 2025.05

D.I. Park, H.R. Lee and S.H. Lee "Evaluation of HICs Based on the Type a Transport Package Requirement" KRS spring meeting, Busan, Korea, 2025. 05

G.H. Jeong and S.H. Lee "Simulation of bending behavior of high burnup spent nuclear fuel rod considering progressive breakage of interfacial bond" KRS autum meeting, 2024.11

S.Y. Kim and S.H. Lee "Estimation of Fracture Parameters of Spent Nuclear Fuel Cladding with Reoriented Hydride under Pinch Load" KRS autumn meeting, 2024.11

S.Y. Kim and S.H. Lee "Methodologies for Evaluating Spent Nuclear Fuel Cladding Resistance and Damage Ratio: Fracture Parameter Estimation" GLOBAL2024, 2024.10

G.H.Jeong and S.H.Lee "A parametric study on the radionuclides release rates from a spent nuclear fuel transport cask submerged in deep sea" GLOBAL2024, 2024.10

S.Y. Kim and S.H. Lee "Fracture resistance evaluation of spent nuclear fuel cladding with hydrides under pinch load" ICTAM2024, 2024.08

G.H. Jeong and S.H. Lee "Radionuclides release rate calculation from a spent fuel transport cask submerged in deep-sea " ICTAM2024, 2024.08

G.H. Jeong and S.H. Lee "Parameter study of radionuclide release rates for a spent fuel transportation cask submerged in deep sea" KRS spring meeting, 2024.05

S.Y. Kim and S.H. Lee "Estimation of Failure Parameters of RCT Simulation Model of Spent Nuclear Fuel Cladding Using Metamodel" KRS spring meeting, 2024.05

B.J. Kim and S.H. Lee " Cause Analysis of Anti-scatter Film Delamination Phenomenon" KSAE autumn meeting 2023.11

G.H. Jeong and S.H. Lee "A Research on Accumulation of Permanent Deformation of EPS packaging due to Random Vibration" KSAE autumn meeting 2023.11

G.H. Jeong and S.H. Lee "Development of Model for Radionuclides Release Rate Calculation From a Transport Cask Submerged in the Deep Sea" KRS autumn meeting 2023.11

Y.J. Son, S.Y. Kim and S.H. Lee "Development of a simplified model for cask-level drop analysis and calculate fuel rod failure probability" KRS autumn meeting 2023.11

S.Y. Kim and S.H. Lee "Methodology for Evaluation of Fracture Resistance of Irradiated Cladding under Pinch Load" KRS autumn meeting 2023.11

B.J. Kim, G.H. Jeong, H.Y. Jang and S.H. Lee "An Experimental Investigation of the Correlation between Lid Displacement and Leakage Rate of Transport Cask and Application of CFD" KRS autumn meeting 2023.11

H.Y. Jang and S.H. Lee "Pressure limit evaluation codes for Spent Nuclear Fuel cask submerged in deep Sea" KNS autumn meeting 2023.10

S.Y. Kim, Y.J. Son and S.H. Lee "Methodology for Evaluation of Spent Nuclear Fuel Damage Ratio under Horizontal Drop Accident" KNS autumn meeting 2023.10

B.J. Kim, Y.J. Son and S.H. Lee "An Experimental Investigation of the Correlation between Lid Displacement and Release Rate of Transport Cask" KNS autumn meeting 2023.10

G.H. Jeong, J.H.Lee and S.H. Lee "Development of model to evaluate thermal fluid flow around a submerged transport cask of spent nuclear fuel in the deep sea " PATRAM22  2023.06

S.Y. Kim, J.H. Lee and S.H. Lee "Development of Microstructure Based Fracture Prediction Model for Zircaloy-4 Cladding With Hydride Under Pinch Load" PATRAM22 2023.06

S.Y. Kim, B.J. Kim and S.H. Lee "Comparison of Simplification Methodology for High Burnup  Spent Nuclear Fuel Rod under Lateral Impact" PATRAM22 2023.06

J.H. Lee, S.Y. Kim and S.H. Lee "Sensitivity analysis of model parameters on the fracture resistance of SNF cladding with hydride" KRS spring meeting 2023.05

H.Y. Jang, J.Y. Park and S.H. Lee "Pressure limit analysis code for spent nuclear fuel transport cask submerged in deep sea" KRS spring meeting 2023.05

B.J. Kim, Y.J. Son, J.H. Lee and S.H. Lee "An Experimental Investigation of the Correlation between Lid Displacement and Leakage Rate of Transport Cask" KRS spring meeting 2023.05

G.H. Jeong, J.H. Lee and S.H. Lee "Development of Model for Radionuclides Release Rate Calculation from A Transport Cask Submerged in the Deep Sea" KNS spring meeting 2023.05

Y.J. Son, S.Y. Kim and S.H. Lee "Preliminary study for evaluation of spent nuclear fuel failure probability" KNS spring meeting 2023.05

S.Y. Kim, J.H. Lee and S.H. Lee "Development of Fracture Prediction Model for Spent Nuclear Fuel Cladding under Pinch Load Based on Continuum Damage Mechanics" KNS spring meeting 2023.05

B.J. Kim, J.Y. Park and S.H. Lee "Simulation of Bending Behavior of High Burnup Spent Fuel Rod Considering Breakage of Interfacial Bonding" KNS spring meeting 2023.05

G.H. Jeoung, S.Y. Kim, S.H. Lee "Development of model to evaluate thermal fluid flow around a submerged transport cask of spent nuclear fuel in the deep sea" KRS autumn meeting 2022.10

J.Y. Park, H.Y. Jang and S.H. Lee "Development of Code for Pressure Resistance Evaluation of Spent Nuclear Fuel transport Cask Submerged in the sea" KRS autumn meeting 2022.10

S.Y. Kim, J.H. Lee and S.H. Lee "Development of Failure Prediction Model for Zircaloy-4 Cladding with Hydride under Pinch Load" EAFORM2022 2022.10

S.Y. Kim, Y.J. Son and S.H. Lee "Comparison of Simplified Models for High Burnup Spent Nuclear Fuel Rod under Lateral impact" EAFORM2022 2022.10

G.H. Jeong, S.Y. Kim and S.H. Lee "A Research on Accumulation of Permanent Deformation of EPS packaging due to Random Vibration" KSAE CAE 2022.05

S.Y. Kim, Y.J. Son and S.H. Lee "Development of Simplified Model of High-Burnup Spent Nuclear Fuel" KSAE CAE 2022.05

B.J. Kim, J.Y. Park and S.H. Lee "Development of Finite Element Model of Adhesive Tape for Packaging" KSAE CAE 2022.05

S.Y. Kim and S.H. Lee "A study on the barrier effect model for radioactive material release rate estimation into the ocean" KRS spring meeting 2022.05

S.Y. Kim, Y.J. Son and S.H. Lee "A Study on the Applicability of Simplified Model of High Burnup Spent Fuel Rod Using Stress Correction Factor in Vertical and Horizontal Drop Impact" KRS spring meeting 2022.05

S.Y. Kim, J.H. Lee and S.H. Lee "Development of Failure Prediction Model for Zircaloy-4 Cladding With Hydride under Pinch Load" KRS spring meeting 2022.05

S.Y. Kim and S.H. Lee "Proposal of Failure Criterion Using Membrane Plus Bending Stress of Stress-Based for the Calibration of Simplified Model of High Burnout Spent Fuel Rods" ACSMO2022 2022.05

S.Y. Kim and S.H. Lee "Comparative Analysis of Simplified Model Developed Considering Two Failure Criteria of a High Burnup Spent Nuclear Fuel Rod" KRS autumn meeting 2021.11

S.Y. Kim and S.H. Lee "Calibration of Simplified Beam Model Properties of High Burnup Spent Nuclear Fuel Rods Considering Membrane Plus Bending Stress Failure Criterion" KRS autumn meeting 2021.11

S.Y. Kim and N.H. Kim and S.H. Lee "Remarks on Identifying Damage Location, Orientation, and Size Using Lamb Wave for Structural Health Monitoring" PHMAP2021 2021.09

S.H. Lee and S.Y. Kim "Equivalent Beam Model for High Burnup Spent Nuclear Fuel Rod" ACSMO 2020.11

S.H. Lee and H.J. Choi "Design Improvement of Anti-Vibration Rubber Assembly using Taguchi Method" MOVIC 2018.08

H.J. Choi and S.H. Lee "Shape Optimal Design of Anti-Vibration Rubber Assembly to Reduce the Vibration of a Tractor Cabin" ACSMO 2018.05

B. Almomani and D.C. Jang and S.H. Lee "Sensitivity Study for Spent Nuclear Fuel Rod Integrity Under Drop Accident Condition" Global2017.09

B. Almomani and D.C. Jang and S.H. Lee "Structural Integrity Assessment of Spend Nyclear Fuel Rod under Drop Accident Condition" SMiRT2017.08

S.H. Lee and B. Amomani and D.C. Jang and H.G. Kang "A PSA framework for an Interim Dry Storage Facility Subjected to an Aircraft Crash" PHM AsiaPacific 2017.07

S.H. Lee and B. Almomani and D.C. Jang and H.G. Kang "An integrated framework of risk assessment for spent nuclear fuel storage facility under aircraft crash" WCSMO17 2017.06

B. Almomani and S.H. Lee and H.G. Kang "PROBABILISTIC RISK ASSESSMENT OF INTERIM DRY STORAGE FACILITY SUBJECTED TO AN AIRCRAFT IMPACT" PASM13 2016.11

B. Almomani and S.H. Lee and H.G. Kang "Probabilistic Risk Assessment Procedure of an Interim Dry Storage Facility for Spent Nuclear Fuel under Aircraft Strike" ISSAT_RQD 2016.08