Program Technical Session

Pacific Basin Nuclear Conference 2026
- In conjunction with KAP 2026

 

"Nuclear Energy for an AI-powered World"

April 22-24, 2026 / Busan, Republic of Korea | BEXCO

Technical Session Program

08:30 - 09:00 Registration
09:00 - 10:20 Technical Sessions
TA-1 Room 101
1. AI Application for Nuclear Innovation
AI: Agent for Nuclear Innovation 1-1
Chair: TBD
  • ABST-000054 09:00-09:20 (20')
    Development of Domain Specific Language Model for Operator Support in Heat Pipe cooled Microreactor System
    Mr. Ik Jae Jin Ulsan National Institute of Science and Technology (UNIST)
  • ABST-000122 09:20-09:40 (20')
    Development of an Agentic AI System Architecture for Multi-Operator Main Control Room: Comparative Evaluation with Single-Agent Frameworks
    Mr. Joo-Won Cha Korea Atomic Energy Research Institute (KAERI); University of Science and Technology (UST)
  • ABST-00128 09:40-10:00 (20')
    Research on MPC-PID Control Strategy for Pressurizer Based on the Two-Region Non-Equilibrium Model
    Ph.D. Hongyang Wei Harbin Engineering University
  • ABST-00167 10:00-10:20 (20')
    Fine-Tuned Large Language Model for MELCOR No-Coding: the FLAMENCO Project
    Prof. Joongoo Jeon POSTECH
TB-1 Room 102
2. Advanced Reactors
Advanced Reactor – Nuclear Physics and Fission Gas
Chair: Yoon Hee LEE
  • ABST-000129 09:00-09:20 (20')
    Study on Neutronic Characteristics of Channels in a Fast Neutron Research Reactor
    Ph.D. Yun Cai Nuclear Power Institute of China
  • ABST-000230 09:20-09:40 (20')
    Feasibility Study of Transuranic-Burning Molten Salt Fast Reactor Cores with Various Configurations for Maritime Applications
    Prof. Yoonhee Lee Jeonbuk National University
  • ABST-000039 09:40-10:00 (20')
    Neutronic Analysis of a Hybrid Fuel Cycle Between Maritime and Terrestrial Fluoride-Salt-Cooled High-Temperature Reactors
    Mr. Josef Ali Hasan Hisanawi Oslo university
  • ABST-000103 10:00-10:20 (20')
    Numerical Simulation Study on Aerosol Deposition and Rebound Characteristics in the Cladding-Pellet Gas Gap of Lead-Bismuth Reactors
    Mr. Huang Kaixin Harbin Engineering University
TC-1 Room 106
7. Modeling and Simulation
Space & Micro Reactors
Chair: Aoguang Wu
  • ABST-000053 09:00-09:20 (20')
    Design of an Integrated Management Simulation System for Space Nuclear Reactor Power Sources
    Dr. Xiao Luo Deep Space Exploration Laboratory
  • ABST-000063 09:20-09:40 (20')
    Transient Safety Characteristics Analysis of SAFE-400 Space Nuclear Reactor
    Dr. Gao Xing China Institute of Atomic Energy
  • ABST-000066 09:40-10:00 (20')
    Neutronic-Thermal-Mechanical Coupling Analysis of a Rod-Type Heat Pipe Reactor Core
    Ph.D. Aoguang Wu University of Science and Technology of China
  • ABST-000092 10:00-10:20 (20')
    Modeling and Transient Analysis of FSP Space Nuclear Reactor System
    Prof. Chi Xu China Institute of Atomic Energy
TD-1 Room 107
6. Nuclear Safety, Security, and Regulatory Compliance
Nuclear Safety, Security, and Regulatory Compliance 1
Chair: Kyungmin KANG
  • ABST-000068 09:00-09:20 (20')
    Multi-Unit Probabilistic Safety Assessment (MUPSA) Regulatory Framework Development in Korea
    Dr. Kyungmin KANG Korea Institute of Nuclear Safety
  • ABST-000124 09:20-09:40 (20')
    Research on the Impact and Response Strategies of Extreme Natural Disasters on the Safety of Nuclear Power Plants in China
    Mr. Jian Hu China Institute of Nuclear Industry Strategy
  • ABST-000144 09:40-10:00 (20')
    Advancing Nuclear Governance through an Integrated Framework for Strengthening Nuclear Safety, Security, and Regulatory Compliance in Emerging Nuclear Energy Programs
    Ms. Bogalech Tiefu Kejela Ethiopian Technology Authority
  • ABST-000256 10:00-10:20 (20')
    Regulatory Developments for Nuclear Power Plants in Taiwan
    Mr. Yen-Fu Chen Nuclear Safety Commission, ROC
TE-1 Room 108
3.Water-Cooled SMRs
Water-Cooled SMRs 1
Chair: Prof. Jee Hyun Seong
  • ABST-000220 09:00-09:20 (20')
    Assessment of Thermal Margin in IVR-ERVC Strategy for i-SMR During Severe Accidents
    Mr. Dong-Hun Shin Korea Advanced Institute of Science and Technology
  • ABST-000168 09:20-09:40 (20')
    Applying PSA-Based Insights to the Design of a Fail-Safe Passive Safety System in an SMR
    Ph.D. Sung-Min Shin Korea Atomic Energy Research Insitute
  • ABST-000097 09:40-10:00 (20')
    Numerical Investigation for Design Feasibility of PIUS-Type Experimental Apparatus with Inherent Safety Features
    Mr. Ju Hun Jung Ulsan National Institute of Science and Technology(UNIST)
  • TBD 10:00-10:20 (20')
    TBD
TF-1 Room 109
5. Innovative Operation and Maintenance
Innovative Operation and Maintenance 1
Chair: Dr. Won Se YOUL(KHNP)
  • ABST-000161 09:00-09:20 (20')
    Non-Invasive Digitization of Existing Nuclear Power Plants
    Mr. Harry Sim Cypress Envirosystems, Inc.
  • ABST-000178 09:20-09:40 (20')
    From Periodic to Predictive: Development of AI-Based Predictive Maintenance Technology for Nuclear Digital I&C System
    Dr. Ji Hun Park Korea Atomic Energy Research Institute
  • ABST-000148 09:40-10:00 (20')
    Prediction of Operational Characteristics in Pressurized Water Reactor LOCA Scenarios Using Multidimensional Correlation Analysis and Artificial Intelligence Modeling
    Ph.D. Yifan XU Harbin Engineering University
  • ABST-000088 10:00-10:20 (20')
    Design and Development of a Mobile Robot for Water Surface Cleaning of Nuclear Power Plant Spent Fuel Pools
    Mr. Jie Li China Nuclear Power Engineering Co., Ltd.
TG-1 Room 110
1. AI Application for Nuclear Innovation
AI: Generals 1-2
Chair: Wenshun Duan
  • ABST-000196 09:00-09:20 (20')
    Research on Open Set Diagnosis Method for Nuclear Power Plants Based on Fault Causal Path Coefficient Identification
    Mr. Xin Wang Harbin Engineering University
  • ABST-000095 09:20-09:40 (20')
    Accident Diagnosis of Natural Circulation Lead-Bismuth Fast Reactor NCLFR-Oil based on Data-Driven
    Dr. Wenshun Duan Chengdu University of Technology
  • ABST-000134 09:40-10:00 (20')
    Semantic Modelling Framework to Enable Scalable Machine Learning Practices in the Nuclear Industry
    Mr. Rajinder Khurmi Ontario Tech University
  • ABST-000143 10:00-10:20 (20')
    AI-Enabled Quality Assurance Framework for Enhancing Reliability and Regulatory Compliance in Small Modular Reactors
    Mr. Nigel George Raphael Ontario Tech University – Nuclear Career Accelerator Program (NCA)
10:20 - 10:40 Coffee Break
10:40 - 12:00 Technical Sessions
TA-2 Room 101
1. AI Application for Nuclear Innovation
AI: Digital Twin Technologies 1-3
Chair: Joongoo Jeon
  • ABST-000055 10:40-11:00 (20')
    Enabling long-Term simulation of 3D natural circulation through a residual-Guided AI-CFD hybrid method
    Ph.D. Shilaj Baral Jeonbuk National University
  • ABST-000074 11:00-11:20 (20')
    Benchmarking Traditional and Data-Driven AI Heat Transfer Correlations for Nusselt Number Prediction in Wire-Wrapped Fuel Assemblies
    Ms. Kexin Ji China Institute of Atomic Energy
  • ABST-000107 11:20-11:40 (20')
    Data-Driven Reduced-Order Modelling of Light Water Reactor Fuel Behavior Under Steady-State Operation
    Mr. Hao Wu Harbin Engineering University
  • ABST-000125 11:40-12:00 (20')
    AI-Driven Digital Transformation in Nuclear Power Engineering: China's Practice and Innovation
    Dr. Xian An China Institute of Nuclear Industry Strategy
TB-2 Room 102
2. Advanced Reactors
Advanced Reactor – Heat Pipe Reactor I
Chair: In Cheol Bang
  • ABST-000027 10:40-11:00 (20')
    Nuclear Power Institute of China
    Mr. Suyi Zhang Nuclear Power Institute of China
  • ABST-000058 11:00-11:20 (20')
    Experimental Study on the Optimal Filling Ratio for Vertical Sodium Heat Pipe
    Mr. Jisung Oh Ulsan National Institute of Science and Technology (UNIST)
  • ABST-000060 11:20-11:40 (20')
    Design of an Automated Control Strategy for Zero-Power Startup in Space Heat Pipe Cooled Reactors Using a High-Fidelity Multiphysics Framework
    Dr. Weixiang Wang Deep Space Exploration Laboratory
  • ABST-000091 11:40-12:00 (20')
    Rapid Prediction Method for the KRUSTY Reactor Core Temperature Field Based on POD and Multi-Point Temperature Measurements
    Dr. Yang Li China Institute of Atomic Energy
TC-2 Room 106
7. Modeling and Simulation
Passive Safety & Natural Circulation
Chair: Ting Hou
  • ABST-000022 10:40-11:00 (20')
    Natural Circulation Capability Verification and Heat Transfer Research of New Type PCS/PRS Water Tank
    Ms. Ting Hou China Nuclear Power Engineering CO.LTD,
  • ABST-000048 11:00-11:20 (20')
    Numerical Verification of the Linear Perturbation Stability Criterion for a Single-Phase Natural Circulation Loop System
    Mr. Jiatai Liu China Nuclear Power Engineering Co., Ltd.
  • ABST-000057 11:20-11:40 (20')
    Design and Analysis of the Drain System for the 1/5 Scaled MSRE Mock-Up Facility: Compact Hydraulic Apparatus for Nuclear Experimental Liquid fuel reactors (CHANEL)
    Ms. Hyeon Ji Kim Ulsan National Institute of Science and Technology
  • ABST-000083 11:40-12:00 (20')
    Numerical Study on Heat Transfer Performance of Separated Heat Pipe in Spent Fuel Pool
    Mr. Jie Li China Nuclear Power Engineering Co., Ltd.
TD-2 Room 107
6. Nuclear Safety, Security, and Regulatory Compliance
Nuclear Safety, Security, and Regulatory Compliance 2
Chair: Gang Li
  • ABST-000064 10:40-11:00 (20')
    Performance Evaluation of Li-6 Based Neutron Detectors for Radiation Portal Monitor Application
    Dr. Gang Li Canadian Nuclear Laboratories
  • ABST-000065 11:00-11:20 (20')
    Sensor Network and Machine Learning Algorithm for Moving Source Detection
    Dr. Gang Li Canadian Nuclear Laboratories
  • ABST-000201 11:20-11:40 (20')
    Study on Methodologies of Evaluation for Environmental Aging Mechanism of Polymer Component in AOV for NPP
    Mr. Seongyun Jo CRI, KHNP
  • ABST-000233 11:40-12:00 (20')
    Comparative Evaluation of ISA and GUM based Uncertainty Evaluation Methods Under HELB Induced Bias for Nuclear Safety Instrumentation
    Mr. Eungse Oh GINIS
TE-2 Room 108
3.Water-Cooled SMRs
Water-Cooled SMRs 2
Chair: Dr. Sang Gyu Lim
  • ABST-000171 10:40-11:00 (20')
    Experimental Study on Critical Heat Flux of Downward-Facing Surface under High-Pressure Conditions Thermal Limit Assessment for i-SMR IVR-ERVC
    Ms. Young Hee Kim Korea Advanced Institute of Science and Technology (KAIST)
  • ABST-000238 11:00-11:20 (20')
    A study of identifying mechanical-Induced vibration loads generated by multiple reactor coolant pumps and their path contribution evaluation
    Ms. Ji hyeon Lee Kyung Hee University
  • ABST-000236 11:20-11:40 (20')
    Experimental Study of External Condensation Heat Transfer under Pure Steam Conditions on a Vertical Tube
    Mr. Sang Gyun Nam Pusan National University
  • TBD 11:40-12:00 (20')
    TBD
TF-2 Room 109
5. Innovative Operation and Maintenance
Innovative Operation and Maintenance 2
Chair: Dr. Won Se YOUL(KHNP)
  • ABST-000018 10:40-11:00 (20')
    The Re-Validation of Time Limited Ageing Analysis - A Case Study
    Ms. Ummash Nasir Government of Pakistan
  • ABST-000023 11:00-11:20 (20')
    Revisiting the 4:1 Rule: Practical Implementation of ASME NQA-1 Requirement 12 Section 302 Reference Standards
    Mr. Jinhong Joo Korea Foundation of Nuclear Safety
  • ABST-000140 11:20-11:40 (20')
    CANDU Feeder Pipe FAC Wall Thinning Rate Analysis and Comparison Between Two Reactor Faces
    Ph.D. Ming Li Ontario Power Generation Inc.
  • ABST-000206 11:40-12:00 (20')
    A Study of Age-Related Degradation Mechanisms on Reactor Vessel Internals for Continued Operation
    Ph.D. Jae-Min Jyung Korea \Hydro & Nuclear Power Company
TG-2 Room 110
1. AI Application for Nuclear Innovation
AI: Generals 1-2
Chair: Emad Alsyed
  • ABST-000156 10:40-11:00 (20')
    Interpretable AI-Based Fault Diagnosis for Nuclear Power Plant Primary Circuits via Cross-Modal Contrastive Learning and Causal Graph Neural Networks
    Prof. Hang Wang Harbin Engineering University
  • ABST-000164 11:00-11:20 (20')
    Open-Set Domain Adaptation Framework for Data-Driven Fault Diagnosis of Nuclear Power Plants
    Mr. Taixi Zhang Harbin Engineering University
  • ABST-000262 11:20-11:40 (20')
    Data Driven Prediction of Nuclear Binding Energy per Nucleon Using Interpretable Machine Learning and Open Source Nuclear Data
    Dr. EMAD ALSYED Faculty of Engineering, King Abdulaziz University, Jeddah, Saudi Arabia
  • ABST-000180 11:40-12:00 (20')
    Generalization Enhancement of Data-Driven Fault Diagnosis Model for Nuclear Power Plants Based on Adversarial Neural Networks
    Ph.D. Zhenfeng Niu Harbin Engineering University
12:00 - 13:00 Lunch Break
08:30 - 09:00 Registration
09:00 - 10:20 Technical Sessions
TA-3 Room 101
1. AI Application for Nuclear Innovation
AI: Agent for Nuclear Innovation 1-1
Chair: TBD
  • ABST-000173 09:00-09:20 (20')
    Design of a LangGraph-Based Multi-Agent Co-Pilot Framework for Operation Support during Nuclear Power Plant Abnormal Situations
    Ph.D. Jeonghun Choi Korea atomic energy research institute
  • ABST-000176 09:20-09:40 (20')
    Reinforcement Learning-Based Variable Universe Fuzzy Control Method Design for the PWR Power Control System
    Ph.D. Hetao Sun Harbin Engineering University
  • ABST-000202 09:40-10:00 (20')
    AI-Agent Framework for Automated Regulatory Search and Analysis in Nuclear Licensing
    Ms. Jongwon Lee RX Inc.
  • ABST-000231 10:00-10:20 (20')
    Development of an AI-Based Intelligent Decision Support System for Nuclear Power Plant Operations: ADVISOR
    Ph.D. Young Ho Chae Korea Atomic Energy Research Institute
TB-3 Room 102
2. Advanced Reactors
Advanced Reactor – Heat Pipe Reactor II
Chair: Chang Soo KIM
  • ABST-000056 09:00-09:20 (20')
    Experimental Study on the Effects of Multiple Welding Joints in Multi-Segment Annular Screen Wick Structures on Heat Pipe Performance for Heat Pipe Microreactor
    Mr. Almanzo Arjuna Ulsan National Institute of Science and Technology (UNIST)
  • ABST-000082 09:20-09:40 (20')
    Study And Analysis On The Low Enriched Uranium Lunar Reactor System Of 100 KWe
    Mr. SHUO JIANG China Institute of Atomic Energy
  • ABST-000059 09:40-10:00 (20')
    Progressive Corrosion Degradation and Early Dry-Out Behavior in Annular-Screen Wick Heat Pipes: Experimental Investigation on Performance
    Ms. Faruk Celik Ulsan National Institute of Science and Technology (UNIST)
  • ABST-000150 10:00-10:20 (20')
    Analysis of loop volume influence characteristic for He-Xe Brayton reactor system
    Ph.D. Haoyang Liao Harbin Engineering University
TC-3 Room 106
7. Modeling and Simulation
Advanced Control & AI-Aided Systems
Chair: Zhonghua Cheng
  • ABST-000110 09:00-09:20 (20')
    Heat Transfer Coefficient Estimation and Steam Temperature Optimal Control for Steam Generator Under Fouling Conditions Based on Recursive Least Squares and Input-Output Feedback Linearization
    Ph.D. Zhonghua Cheng Tsinghua
  • ABST-000214 09:20-09:40 (20')
    Power Level Control of Nuclear Reactor Core Using Optimized T-S Fuzzy PI Sliding Mode Composite Controller Based on Validated Nonlinear Two-Point Kinetics Model
    Dr. Hailemichael Guadie Mengsitu Harbin Engineering University
  • ABST-000034 09:40-10:00 (20')
    A Study on Hybrid Kalman Filter and Monte Carlo-Based State Estimation
    Ph.D. Dongwook Jang jconekorea
  • TBD 10:00-10:20 (20')
    TBD
TD-3 Room 107
6. Nuclear Safety, Security, and Regulatory Compliance
Nuclear Safety, Security, and Regulatory Compliance 3
Chair: Chul Hwan Jung
  • ABST-000165 09:00-09:20 (20')
    CNSC Cyber Security Assessment and Expectation for Nuclear Reactor Designs
    Dr. Chul Hwan Jung Canadian Nuclear Safety Commission
  • ABST-000247 09:20-09:40 (20')
    An Intelligent Compliance Mapping and Evidence Reasoning System for Operational Technology Cybersecurity
    Prof. Fan Zhang Georgia Institute of Technology
  • ABST-000265 09:40-10:00 (20')
    Evolving Software Supply-Chain Threats in the Era of AI-Augmented Cyber Attacks: Implications for Small Modular Reactor (SMR) Systems
    Christopher Panetta Ontario Tech University in Ontario
  • ABST-000159 10:00-10:20 (20')
    Planning a nonproliferation policy for north korea under limited information
    Ph.D. Seon Byeong Kim Korea Atomic Energy Research Institute
TE-3 Room 108
3.Water-Cooled SMRs
Water-Cooled SMRs 3
Chair: Dr. Jin-Hwa Yang
  • ABST-000203 09:00-09:20 (20')
    Characteristics of an Integral Effect Test Facility for Validation of Passive Safety Systems in the i-SMR
    Ph.D. Jin-Hwa Yang Korea Atomic Energy Research Institute
  • ABST-000242 09:20-09:40 (20')
    Validation of a 1-D System Code for an Air-Cooled Vertical Heat Pipe: Effects of Filling Ratio and Air Flow Rate
    Mr. Yonadan Choi Korea Advanced Institute of Science and Technology
  • ABST-000204 09:40-10:00 (20')
    Effects of Secondary Side Channel Arrangement and Wall Thickness on the Performance of Printed Circuit Steam Generator in a Water-Cooled SMR
    Dr. Hyunjun Cho Korea Atomic Energy Research Institute
  • ABST-000062 10:00-10:20 (20')
    Simulation Study for a Novel Superheated Steam Supply System of NHR200-II Based on Modelica
    Mr. Zepeng Liu Huazhong University of Science and Technology
TF-3 Room 109
11. Public Acceptance, Human Resources & Knowledge Management
Public Acceptance, Human Resources & Knowledge Management 1
Chair: Youngmi Nam
  • ABST-000032 09:00-09:20 (20')
    SMRs Driving New Energy Markets: Empirical Insights from Demand-Driven Urban Siting
    Ms. Gaeul Choi Seoul National University
  • ABST-000078 09:20-09:40 (20')
    Knowledge Management for the Nuclear Industry: Connecting Information for Smarter Decision-Making
    Ms. Karine King Accuris
  • ABST-000170 09:40-10:00 (20')
    High-Reliability Nuclear Knowledge Graph Construction via Rule-Guided LLM Fine-Tuning
    Ph.D. Shangcai Zheng Harbin Engineering University
  • ABST-000205 10:00-10:20 (20')
    Development and Outcomes of Training Program on Nuclear Infrastructural Issues for the Kenya Nuclear Power Program
    Dr. Youngmi Nam Korea Atomic Energy Research Institute
TG-3 Room 110
9. Waste Management, Spent Fuel & Decommissioning
Waste Management, Spent Fuel & Decommissioning 1
Chair: Glenn Harvel
  • ABST-000079 09:00-09:20 (20')
    Study on Decommissioning Indicators for High-Quality Development of Nuclear Industry in China
    Ph.D. Lei Shi China Institute of Nuclear Industry Strategy
  • ABST-000118 09:20-09:40 (20')
    Development of High-Removal Treatment Process for Radioactive Laundry Wastewater
    Ms. Yessika Natalia Chelsie University of Science and Technology
  • ABST-000139 09:40-10:00 (20')
    Modelling of Reactor Core Concrete Activation for Estimation of Waste Concrete Volumes
    Prof. Glenn Harvel Ontario Tech University
  • ABST-000157 10:00-10:20 (20')
    Electrochemical Advanced Oxidation Processes for Sustainable Degradation of Polychlorinated Biphenyls
    Dr. Lin Li Canadian Nuclear Laboratories
10:40 - 12:00 Technical Sessions
TA-4 Room 101
1. AI Application for Nuclear Innovation
AI: Digital Twin Technologies 1-3
Chair: Ricardo Vinuesa
  • ABST-000071 10:40-11:00 (20')
    DeepONet-Based Surrogate Model for CFD Simulations in Small Modular Reactor Digital Twin
    Mr. Minseo Lee Jeonbuk National University
  • ABST-000153 11:00-11:20 (20')
    A General NN-EnKAPF Framework for Real-Time Monitoring of Nuclear Reactors: Joint Estimation of States and Unmeasurable Parameters
    Ms. Ziyan Du Shanghai Jiao Tong University
  • ABST-000209 11:20-11:40 (20')
    Bridging 0D Thermal-Hydraulics Models and CFD though Data-Assimilation: A Digital Twin approach for Diagnosis in Fast Reactors
    Dr. Matilde Fiore von Karman Institute for Fluid Dynamics
  • TBD 11:40-12:00 (20')
    TBD
TB-4 Room 102
2. Advanced Reactors
Advanced Reactor – Molten Salt Reactor
Chair: Seog CHO
  • ABST-000073 10:40-11:00 (20')
    Investigation of Design Feasibility for Cartridge Type Molten Salt Reactor Concept through CFD Analysis
    Ms. Seolhui Kim Ulsan National Institute of Science and Technology (UNIST)
  • ABST-000109 11:00-11:20 (20')
    A Multi-Dimensional Coupled Simulation Framework for the Molten Salt Fast Reactor System Based on GeN-Foam and a Surrogate Model
    Ms. Qi Ya Jiang Harbin Engineering University
  • ABST-000142 11:20-11:40 (20')
    Experimental Investigation of the Effectiveness of a Vortex Breaker in the MSR Drain System
    Mr. Joo Hyung Seo UNIST
  • ABST-000229 11:40-12:00 (20')
    Characterization of Molten Salt Composition and Thermophysical Properties using a Dual Electrochemistry/Thermal Conductivity Probe (DETP)
    Prof. Matthew J Memmott Brigham Young University
TC-4 Room 106
7. Modeling and Simulation
High-Fidelity Flow Modeling
Chair: TBD
  • ABST-000210 10:40-11:00 (20')
    Local Reynolds number and Prandtl number dependent thermal wall function development based on DNS data of a turbulent boundary layer flow
    Dr. Matilde Fiore von Karman Institute for Fluid Dynamics
  • ABST-000029 11:00-11:20 (20')
    A multiphase moving-Particle-Semi-Implicit model for simulating interfacial flows
    Ph.D. Lijun Jian China Nuclear Power Engineering Co., Ltd
  • ABST-000120 11:20-11:40 (20')
    Hybrid OpenMP/MPI Parallelism for Accelerating Complex-Geometry 3D Discrete Ordinates Particle Transport
    Ph.D. Yingchi Yu Chinese Academy of Sciences
  • TBD 11:40-12:00 (20')
    TBD
TD-4 Room 107
4. Marine Nuclear Power
Marine Nuclear Power
Chair: TBD
  • ABST-000234 10:40-11:00 (20')
    Coupled OpenMC–PRK–Fluent Framework for Transient Neutronics–Thermal-Hydraulics of a Marine MSFR under Rolling Motion
    Mr. Yongse Kim Korea Advanced Institute of Science and Technology (KAIST), Daejeon, Republic of Korea
  • ABST-000093 11:00-11:20 (20')
    Coupled PROTEUS-NODAL and SAM Analysis of a Maritime Molten Salt Reactor
    Ph.D. Han Gyu Lee University of Michigan
  • ABST-000219 11:20-11:40 (20')
    Numerical Investigation on the Effect of Ship Rolling Motion on Solidification in Freeze Valve of a Marine Molten Salt Reactor (MARINA)
    Mr. Hyoung suk Yu Korea Advanced Institute of Science and Technology
  • ABST-000215 11:40-12:00 (20')
    Examining the Role of Flag States in Enforcing Nuclear Security and Safeguards Onboard Floating Nuclear Power Plants
    Mr. Marc Fialkoff Oak Ridge National Laboratory
TE-4 Room 108
8. Nuclear Fuel and Materials
Nuclear Fuel and Materials 1_Innvoative approach in nuclear fuel and materials
Chair: TBD
  • ABST-000123 10:40-11:00 (20')
    An Analysis of the Nuclear Fuel Industry's Distinctive Features
    Mr. Hongli Huang ‌CNNC Jianzhong Nuclear Fuel Co., Ltd.‌
  • ABST-000172 11:00-11:20 (20')
    Investigation of In-Situ Nano Oxide Formation in Fe-ODS Steels Produced by L-DED
    Ph.D. Suk Hoon Kang Korea Atomic Energy Research Institute
  • ABST-000228 11:20-11:40 (20')
    Tritium release behavior of Li2TiO3 breeders irradiated by 14 MeV fusion neutrons at INEST, CAS
    Prof. Haixia Wang Hefei Institutes of Physical Science, Chinese Academy of Sciences (HFIPS, CAS)
  • ABST-000158 11:40-12:00 (20')
    Evaluation of New Material to Enhance the Yield of TRU Nuclear Fuel Fabrication for Casting Crucible
    Ph.D. Sang-Gyu Park Korea Atomic Energy Research Institute
TF-4 Room 109
11. Public Acceptance, Human Resources & Knowledge Management
Public Acceptance, Human Resources & Knowledge Management 2
Chair: Yeonhee Hah
  • ABST-000184 10:40-11:00 (20')
    Strengthening Nuclear Safety Through Integrated Knowledge Management and Leadership Development: Insights from the IAEA School on Nuclear and Radiological Leadership for Safety
    Ms. Yeonhee Hah Korea Institute of Nuclear Safety
  • ABST-000192 11:00-11:20 (20')
    Participation Motivations of International Professionals in the Radiopharmaceutical Continuing Professional e-Learning Programme
    Dr. Hyeon-Jin Kim Korea Atomic Energy Research Institute
  • ABST-000252 11:20-11:40 (20')
    A framework for values-Sensitive design of advanced reactor systems
    Prof. Aditi Verma University of Michigan
  • ABST-000255 11:40-12:00 (20')
    Toys for the Third Nuclear Age: A First-Year Engineering Course Aimed at Changing the Nuclear Narrative for Improved Creativity, Care, and Acceptance
    Dr. Katie L Snyder University of Michigan
TG-4 Room 110
10, Nuclear Hydrogen and Other Integrated Applications
Nuclear Hydrogen and Other Integrated Applications
Chair: Dr. Charkas Hasan
  • ABST-000160 10:40-11:00 (20')
    Technical Optimization and Economic Analysis of Steam Supply from the HPR1000
    Ms. Ping WANG China Nuclear Power Engineering Corporation
  • ABST-000163 11:00-11:20 (20')
    Research Progress and Prospects of Integrated Applications of Nuclear Energy in China
    Ms. Ping WANG China Nuclear Power Engineering Corporation
  • ABST-000175 11:20-11:40 (20')
    Techno-Economic Feasibility Assessment of SMR-LTE using PEPSE Modeling
    Mr. Jongseol Moon Korea Hydro and Nuclear Power-Central Research Institute (KHNP-CRI)
  • ABST-000185 11:40-12:00 (20')
    Feasibility Analysis and Potential Application Scenarios of Retrofitting Coal-Fired Power Plants to Nuclear Power Plants in China
    Mr. Yibo Luo China Nuclear Power Engineering Co., Ltd.
12:00 - 13:00 Lunch Break
08:30 - 09:00 Registration
09:00 - 10:20 Technical Sessions
TA-5 Room 101
1. AI Application for Nuclear Innovation
AI: Agent for Nuclear Innovation 1-1
Chair: TBD
  • ABST-000250 09:00-09:20 (20')
    Development of Small Modular Reactor Operation Support System based on Agentic Artificial Intelligence Framework
    Ph.D. Seung Geun Kim Korea Atomic Energy Research Institute
  • ABST-000266 09:20-09:40 (20')
    OECD Nuclear Energy Agency Joint Project on an AI Platform for Nuclear Research and Education (AIxpertise)
    Mr. Shahab Dabiran OECD Nuclear Energy Agency (NEA)
  • ABST-000111 09:40-10:00 (20')
    Agentic AI Framework for Assisting PINN Workflows in Nuclear Thermal Analysis
    Mr. Jaejun Lee University of Science & Technology
  • TBD 10:00-10:20 (20')
    TBD
TB-5 Room 102
2. Advanced Reactors
Advanced Reactor – High Temperature Reactor and Proliferation Resistance
Chair: Byung Ha PARK
  • ABST-000221 09:00-09:20 (20')
    CFD Analysis of Cross-Gap and Heat-Generation Distribution Effects in Prismatic HTGR Fuel Blocks
    Mr. Yonghyeon Na Korea Advanced Institute of Science and Technology (KAIST)
  • ABST-000224 09:20-09:40 (20')
    HECTAR: High Temperature Gas-Cooled Reactor for Industrial Process Heat
    Ph.D. Chan Soo Kim Korea Atomic Energy Research Institute
  • ABST-000232 09:40-10:00 (20')
    CFD Analysis of Cross-Gap and Inner Control-Rod Gap Effects in a Prismatic HTGR
    Mr. Youchan Kim KAIST
  • ABST-000216 10:00-10:20 (20')
    Methodology Development for Proliferation Resistance Optimization of Advanced Reactors and Fuel Cycles
    Ms. Rebecca M Chamberlin Oak Ridge National Laboratory
TC-5 Room 106
7. Modeling and Simulation
Thermalhydraulic System Analysis
Chair: Marwan Hassan
  • ABST-000031 09:00-09:20 (20')
    Modelling of Fuel Bundles Subjected to Flow Excitation
    Prof. Marwan Hassan University of Guelph
  • ABST-000047 09:20-09:40 (20')
    Evaluation and Sensitivity Analysis of Loss of Feedwater for HPR1000 with Kv Scaling Calculation
    Mr. Jiatai Liu China Nuclear Power Engineering Co., Ltd.
  • ABST-000100 09:40-10:00 (20')
    Numerical Simulation on Convective Heat Transfer of Liquid-Metal Flow in a Channel with Gaussian Random Rough Surfaces
    Prof. Wenpei Feng Chengdu University of Technology
  • ABST-000116 10:00-10:20 (20')
    Simulation investigation on helium flow and heat transfer characteristics for very high temperature irradiation
    Mr. Jin Lei Nuclear Power Institute of China
TD-5 Room 107
6. Nuclear Safety, Security, and Regulatory Compliance
Nuclear Safety, Security, and Regulatory Compliance 4
Chair: Gyunyoung Heo
  • ABST-000025 09:00-09:20 (20')
    Planning, Design and Implementation of Nuclear Emergency Exercises in Taiwan
    Mr. Yi-Ta Tsai Nuclear Safety Commission
  • ABST-000033 09:20-09:40 (20')
    Optimizing the Spatiotemporal Deployment of Evacuation Support Resources Under an ABM Simulation Platform
    Mr. Joonseok Lim Kyung Hee University
  • ABST-000051 09:40-10:00 (20')
    Disaster prevention design for Hualong One nuclear power plant nuclear island cooling tower water distribution filler
    Mr. Cang Dao Cheng Hualong Pressurized Water Reactor Technology Corporation,Ltd.
  • ABST-000035 10:00-10:20 (20')
    A Software Framework for Automated Fault Tree Construction from Simplified Piping and Instrumentation Diagrams
    Ms. Jinok Lee Kyung Hee University
TE-5 Room 108
8. Nuclear Fuel and Materials
Nuclear Fuel and Materials 2_Materials design and evaluation
Chair: TBD
  • ABST-000098 09:00-09:20 (20')
    Design and Rrsearch of Multi-Damping SIC Cladding Tube Test Unit Based on Research Reaction Test Loop
    Mr. Lu Meng Kang Nuclear Power of Institute of China
  • ABST-000102 09:20-09:40 (20')
    Molecular Dynamics Simulation of Ag Diffusion in TRISO Kernel SiC Shell Pd Corrosion Product Pd₂Si based on Machine Learning Potential
    Mr. Jiaxuan Liu Harbin Engineering University
  • ABST-000189 09:40-10:00 (20')
    Mechanical Properties of Newly Developed Neutron Absorbing Structural Materials
    Ph.D. Seungmun Jung Korea Atomic Energy Research Institute
  • ABST-000133 10:00-10:20 (20')
    Research on the Emitter Material of Self-Power Fast Neutron Detector
    Ms. Yaohan Hu Nuclear Power Institute of China（Chengdu, Sichuan, China）
TF-5 Room 109
12. Nuclear Economics and Policy
Nuclear Economics and Policy 1
Chair: Seongmin Son
  • ABST-000038 09:00-09:20 (20')
    Estimating Cost of High-Temperature Gas-Cooled Reactor system for Clean Process Heat Production
    Ms. Nayoung Kim Korea Advanced Institute of Science and Technology
  • ABST-000108 09:20-09:40 (20')
    Techno-Economic Comparison of Various Options for Hydrogen Produced from Nuclear Energy in S. Korea
    Mr. Changmin Yoon KAIST
  • ABST-000115 09:40-10:00 (20')
    Global Nuclear Fuel Market: Price Evolution and Supply-Demand Dynamics in the Uranium Conversion and Enrichment Sectors
    Dr. Jiqiang Su China Institute of Nuclear Industry Strategy
  • ABST-000126 10:00-10:20 (20')
    The China Model: Cost-Effective and Efficient Nuclear Power Construction and Its Global Implications
    Dr. Xian An China Institute of Nuclear Industry Strategy
TG-5 Room 110
9. Waste Management, Spent Fuel & Decommissioning
Waste Management, Spent Fuel & Decommissioning 2
Chair: Haruko Wainwright
  • ABST-000217 09:00-09:20 (20')
    ML-Coupled Reactor-To-Repository Framework for Evaluating from Advanced Reactor Spent Nuclear Fuel
    Dr. Haruko M Wainwright Massachusetts Institute of Technology
  • ABST-000263 09:20-09:40 (20')
    Safety and Performance of Deep Borehole Disposal for SMR Waste: Modelling Thermal, Hydraulic, and Mechanical Interactions
    Prof. Gonzalo Zambrano Narvaez University of Alberta
  • ABST-000119 09:40-10:00 (20')
    HADESNU-PF 2.0: Numerical Model for Simulating Pitting Corrosion Behavior of Copper Considering Chloride and Sulfide-Rich Environment
    Mr. Pilhyeon Ju Seoul National University
  • ABST-000253 10:00-10:20 (20')
    More than human design: The environment as stakeholder in waste management and environmental decontamination practices
    Prof. Aditi Verma University of Michigan
10:40 - 12:00 Technical Sessions
TA-6 Room 101
1. AI Application for Nuclear Innovation
AI: Generals 1-2
Chair: Jinfeng Li
  • ABST-000195 10:40-11:00 (20')
    Research on Fault Diagnosis of Nuclear Power Units under Multiple Power Conditions Based on Semi-Supervised Domain Adaptation
    Ph.D. Chenxin Zhu Harbin Engineering University
  • ABST-000085 11:00-11:20 (20')
    Artificial Intelligence Application in Nuclear Power Plants in China
    Prof. Jinfeng Li China Institute of Atomic Energy
  • ABST-000197 11:20-11:40 (20')
    Open-Set Fault Diagnosis for Reactor Systems Based on a Deep Prototype Network
    Mr. Yu Sun Harbin Engineering University
  • ABST-000169 11:40-12:00 (20')
    Assessment of Calibration Methods for Data-Driven Fault Diagnostic Models in Nuclear Power Plants
    Ph.D. Jiahao Cheng Harbin Engineering University
TB-6 Room 102
2. Advanced Reactors
Advanced Reactor – Light Water Reactor and Lead Bismuth Loop
Chair: Seok Kim
  • ABST-000182 10:40-11:00 (20')
    Experimental Study on Droplet Drag Characteristics under Reflooding Conditions
    Dr. Fangdong Wang Harbin Engineering University
  • ABST-000193 11:00-11:20 (20')
    Experimental Results of shaft seal transient test of localized APR1400’s RCP
    Dr. Seok CHO Korea Atomic Energy Research Institute
  • ABST-000075 11:20-11:40 (20')
    Seismic Design Requirement Analysis for Reactor Coolant Pumps
    Ms. BO CHEN China Nuclear Power Engineering Co.
  • ABST-000090 11:40-12:00 (20')
    Conceptual Design and Thermal Analysis of Heat Exchange Zone in Self-Contained Closed Loop
    Ms. Qiyu Liu Nuclear Power Institute of China
TC-6 Room 106
7. Modeling and Simulation
Severe Accident & Model Calibration
Chair: Anton P Pshenichnikov
  • ABST-000045 10:40-11:00 (20')
    Analysis on Condensation Phenomenon with Non-Condensable Gases in the CABLE Test Facility Using GOTHIC and GOTHIC 3D Models
    Ms. Ningxi JIA China Nuclear Power Engineering Co. Ltd, Beijing, China
  • ABST-000104 11:00-11:20 (20')
    Preliminary Validation of a Severe Accident Analysis Code for Core Damaging Scenarios against International Standard Problems
    Mr. Huang Kaixin Harbin Engineering University
  • ABST-000207 11:20-11:40 (20')
    Modelling of the Fukushima Dai-Ichi Multiphase Molten Debris Spreading Using OpenFOAM Software
    Dr. Anton P Pshenichnikov Japan Atomic Energy Agency
  • ABST-000132 11:40-12:00 (20')
    Data-Driven Calibration and Validation of a Multi-Physics Model for Simulating Transients in Fissile Solutions
    Ph.D. Rui Guo China Institute of Nuclear Power
TD-6 Room 107
6. Nuclear Safety, Security, and Regulatory Compliance
Nuclear Safety, Security, and Regulatory Compliance 5
Chair: Jong Tae Kim
  • ABST-000036 10:40-11:00 (20')
    Study on Regulatory Verification Models for Level 1 and Level 2 Probabilistic Safety Assessment of the i-SMR
    Mr. YUNTAE GWAK Kyung Hee University
  • ABST-000187 11:00-11:20 (20')
    Validation of a Numerical Model for a Passive Containment Cooling System Installed in Advanced and Modular Pressurized Water Reactor Containments
    Ph.D. Jong Tae Kim Korea Atomic Energy Research Institute
  • ABST-000070 11:20-11:40 (20')
    Identification Methodology for Equipment Requiring Environmental Qualification
    Mr. Geon Gyu Choi Korea Hydro & Nuclear Power
  • ABST-000086 11:40-12:00 (20')
    Analysis on water hammer in main feedwater system in HPR1000 nuclear power unit
    Mr. Daping Lin China Nuclear Power Engineering Co.,Ltd
TE-6 Room 108
8. Nuclear Fuel and Materials
Nuclear Fuel and Materials 3_Fuel and materials simulation
Chair: TBD
  • ABST-000136 10:40-11:00 (20')
    Thermodynamic and Experimental Degradation Evaluation of UO2 Pellets under the Condition of Fuel Rod Failure
    Ph.D. Taesik Jung KEPCO NF
  • ABST-000243 11:00-11:20 (20')
    Neutronics Calculation of the Conceptual U3Si2-UO2 Duplex Fuel Rod Design for PWR
    Prof. Bin Ye Neutronics Calculation of the Conceptual USi-UO Duplex Fuel Rod Design for PWR
  • ABST-000244 11:20-11:40 (20')
    Studies on Neutronic Performance of Metal (U-6Zr-XAl) Fueled LFR cores
    Prof. Bin Ye Neutronics Calculation of the Conceptual USi-UO Duplex Fuel Rod Design for PWR
  • ABST-000096 11:40-12:00 (20')
    Direct Numerical Simulation of Oxygen Mass Transfer in Lead-Cooled Subchannel
    Prof. Wenpei Feng Chengdu University of Technology
TF-6 Room 109
12. Nuclear Economics and Policy
Nuclear Economics and Policy 2
Chair: Jeong Ik Lee
  • ABST-000145 10:40-11:00 (20')
    Research on the Ways of Dispute Settlement for Nuclear Damage in China
    Prof. Jiu LIU Harbin Engineering University
  • ABST-000254 11:00-11:20 (20')
    A SEMATECH-Style Public-Private Consortium for Small Modular Reactors: Defense-Backed Industrial Development and Remote Power Deployment
    Mr. Bradford Max Arnold University of Texas at Arlington
  • ABST-000264 11:20-11:40 (20')
    Overview of the Next Generation MURR Project: Progress and Scope of the Design Studies
    Ph.D. Kyoungwoo Seo KAERI
  • TBD 11:40-12:00 (20')
    TBD
TG-6 Room 110
9. Waste Management, Spent Fuel & Decommissioning
Waste Management, Spent Fuel & Decommissioning 3
Chair: Jaeyeong Park
  • ABST-000246 10:40-11:00 (20')
    Energy Recovery from Storage and Disposal Facilities for High-Level Nuclear Waste
    Mr. Dauren Sarsenbayev Massachusetts Institute of Technology
  • ABST-000043 11:00-11:20 (20')
    Emerging Trends in Geopolymer Research for Nuclear Waste Management: A Perspective with Case Studies
    Dr. Sajid Iqbal Korea Advanced Institute of Science and Technology (KAIST)
  • ABST-000113 11:20-11:40 (20')
    The Re-Validation of Time Limited Ageing Analysis of Service Building Housing Spent Fuel Pool during Decommissioning Phase
    Ms. Ummash Nasir Government of Pakistan
  • ABST-000117 11:40-12:00 (20')
    STUDY ON THE DEVELOPMENT PATH OF AFR STORAGE FOR SPENT FUEL IN CHINA
    Mr. Jian Hu China Institute of Nuclear Industry Strategy
12:00 - 13:00 Lunch Break