Session Schedule Order.
Panel Session - 01 Development of Light Water Small Modular Reactors
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Date & Time: September 2 (Tue), 10:20-12:25
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Organizer(s):
- Bao-Wen Yang (Delta Energy Group, New York, United States)
- Jun Liao (Westinghouse Electric Company, United States)
- Bin Han (Southeast University, China, People's Republic of)
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Panelists:
- Ju Yeop Park (Korea Institute of Nuclear Safety, Korea, Republic of)
- Yuhong Wang (China Nuclear Power Engineering Company, China, People's Republic of)
- Piyush Sabharwall (daho National Laboratory, United States of America)
- Jun Liao (Westinghouse Electric Company, United States)
- Fulvio Mascari (Italian National Agency for New Technologies, Energy and Sustainable Economic Development, Italy)
- Andrew Christopher Morreale (Canadian Nuclear Laboratories, Canada)
- Jose Reyes (NuScale Power, United States)
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Abstract
Small Modular Nuclear Reactors (SMRs) represent a significant advancement in nuclear technology, offering scalable and flexible solutions for clean energy production. This panel session will bring together leading experts to discuss the latest developments, challenges, and opportunities in the development of light water SMRs. Topics will include innovative reactor designs, Experiments, Modeling and simulation, licensing, diverse application, and the role of SMRs in future energy systems.
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Contact Person:
- Bao-Wen Yang (Delta Energy Group, New York, United States)
- Jun Liao (Westinghouse Electric Company, United States)
Panel Session - 02 Successful Continued-Operation Implementation of Nuclear Power Plants through the Overseas
Regulation Frameworks and Key Aging Degradation Issues
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Date & Time: September 2 (Tue), 10:20-11:50
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Venue: Session Room 8 - #108 (1F)
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Organizer(s):
- Bong-Yo Yun (Korea Hydro and Nuclear Power - Central Research Institute, Korea, Republic of)
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Panelists:
- Garry Young (Electric Power Research Institute, United States)
- Sekimura Naoto (The University of Tokyo, Japan)
- Leon Cizelj (Jožef Stefan Institute, Slovenia)
- André Zander (Framatome, Germany)
- Kisig Kang (KEPCO International Nuclear Graduate School, Korea, Republic of)
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Abstract
This session will explore the regulatory framework and key aging management issues essential for the successful continued operation of nuclear power plants beyond their original design life. Expert panelists will discuss safety assessments, regulatory trends, and reliability enhancement strategies, providing insights through real-world case studies to identify optimal approaches for life extension. The objectives and expected outcomes are as follows; Understanding licensing procedures and regulatory development for 20 years life extension, addressing key component degradation issues, and ensuring safety and economic viability for sustainable and effective plant operation. etc.
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Contact Person: Se Youl Won (Korea Hydro and Nuclear Power - Central Research Institute, Korea, Republic of)
Panel Session - 03 International Cooperation in Developing Innovative Nuclear Reactors: Needs, Best Practices,
and Challenges
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Date & Time: September 2 (Tue), 13:10-14:40
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Organizer(s):
- Vladimir Kriventsev (IAEA, Austria)
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Moderators:
- Vladimir Kriventsev (IAEA, Austria)
- Hisashi Ninokata (Institute of Science Tokyo, Japan)
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Panelists:
- Jewhan Lee (Korea Atomic Energy Research Institute, Korea, Republic of)
- Yassin A. Hassan (Texas A&M University, United States)
- Dalin Zhang (Xi'an Jiaotong University, China)
- Hidemasa Yamano (Japan Atomic Energy Agency, Japan)
- Ferry Roelofs (Nuclear Research and Consultancy Group, Netherlands)
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Abstract
At a time when sustainable and secure energy solutions are crucial, innovative nuclear reactor technologies are gaining attention worldwide. This panel, titled "International Cooperation in Developing Innovative Reactors: Needs, Best Practices, and Challenges," brings together experts in nuclear reactor thermal hydraulics who have also spent years working on international collaborations. Their experience comes from joint projects, many of them organized through the IAEA and other global efforts. Rather than focusing only on nuclear thermal hydraulics, the panel will explore why cooperation across countries and international organizations is so important in this field, and what we have learned along the way. Speakers will share models of successful collaborations, as well as examples of the obstacles they have experienced, like misaligned goals, communication gaps, or regulatory barriers. The session aims to offer practical suggestions on how to improve future cooperation and keep progress in the development of sustainable and save nuclear energy systems.
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Contact Person: Vladimir Kriventsev (IAEA, Austria)
Panel Session - 04 Thermal-hydraulics Testing Needs for Advanced Liquid-metal-cooled Reactors
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Date & Time: September 2 (Tue), 16:00-17:30
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Organizer(s):
- Julio Pacio (Belgian Nuclear Research Centre, Belgium)
- Jun Liao (Westinghouse Electric Company, United States)
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Panelists:
- Jewhan Lee (Korea Atomic Energy Research Institute, Korea, Republic of)
- Wenxi Tian (Xi'an Jiaotong University, China, People's Republic of)
- Giuseppe Francesco Nallo (Politecnico di Torino, Italy)
- Julio Pacio (Belgian Nuclear Research Centre, Belgium)
- Hidemasa Yamano (Japan Atomic Energy Agency, Japan)
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Abstract
Several Generation-IV liquid metal fast reactors are being developed worldwide, both cooled by sodium (SFR) and by lead (LFR), with the aim of enhancing safety, sustainability, and efficiency. The successful deployment of these advanced reactors relies on a deep understanding of thermal-hydraulics to ensure reliable operation under normal and off-normal conditions. Experimental testing is essential for validating numerical models, supporting reactor design and safety assessment, and addressing key technological challenges. This panel will bring together experts from research institutions, industry, and licensing bodies to discuss the most pressing thermal-hydraulics testing needs. Key topics will include design and safety requirements, scaling challenges, test facility design, instrumentation for liquid metals, and the integration of experimental data with high-fidelity simulations. The discussion will also explore international collaboration opportunities and the role of existing and future test infrastructures. By highlighting critical gaps and priority research areas, this session aims to foster dialogue on how to advance thermal-hydraulics testing capabilities in support of reactor development and licensing.
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Contact Person: Julio Pacio (Belgian Nuclear Research Centre, Belgium)
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Program:
Panel Session - 05 High Fidelity MSMP (Multi-scale & Multi-physics) Simulation for SMR Development
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Date & Time: September 3 (Wed), 10:20-11:50
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Venue: Session Room 1 - #205 (2F)
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Organizer(s):
- Yun-Je Cho (Korea Atomic Energy Research Institute, Korea, Republic of)
- Elia Merzari (The Pennsylvania State University, United States)
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Moderator(s): Elia Merzari (The Pennsylvania State University, United States)
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Panelists:
- Igor Bolotnov (North Carolina State University, United States)
- Dillon Shaver (Argonne National Laboratory, United States)
- Thomas Höhne (Helmholtz-Zentrum Dresden-Rossendorf, Germany)
- Sofiane Benhamadouche (Électricité de France, France)
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Abstract
Amidst the globally intense competition in SMR development, interest in high-fidelity analysis for design validation of SMRs is also increasing. SMRs such as MSRs, SFRs, HTGRs, and HPRs possess many characteristics that are difficult to analyze with existing design tools, necessitating the utilization of new analysis tools. Fuel characteristics are also changing significantly with molten salt, metallic fuel, and TRISO particles, and the extensive use of fully passive safety systems and compact design makes multi-physics and multi-dimensional analysis essential. For these reasons, most research groups who develop the simulation tools are moving beyond analysis using a single software and actively adopting MSMP (Multi-Scale Multi-Physics) technology.
This trend is further accelerating in conjunction with advancements in supercomputing and GPU technology. Leveraging extensive computational resources, high-reliability analyses that were previously difficult to perform are now feasible, and the feasibility of applying these analytical results within actual regulatory frameworks.
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Contact Person:
- Yun-Je Cho (Korea Atomic Energy Research Institute, Korea, Republic of)
- Elia Merzari (The Pennsylvania State University, United States)
Panel Session - 06 V&V Experiments for SMR Demonstration and Development
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Date & Time: September 3 (Wed), 10:20-11:50
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Organizer(s):
- Stephen M. Bajorek (United States Nuclear Regulatory Commission, United States)
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Panelists:
- Kyoung-Ho Kang (Korea Atomic Energy Research Institute, Korea, Republic of)
- Stephen M. Bajorek (United States Nuclear Regulatory Commission, United States)
- Joëlle Fleurot (Autorité de Sûreté Nucléaire et de Radioprotection, France)
- Casey Tompkins (Karios Power, United States)
- Sanjeev Gupta (Framatome, Germany)
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Abstract
This panel session aims to develop programs for V&V (verification and validation) experiments for SMR demonstration and development. A variety of SMR concepts are being developed around the world, and the progress of the development is variable in different countries. V&V experiments may be planned and performed in different levels of demonstration, development, licensing, and deployment for SMRs. Designing V&V experiments may be based on the scaling methodology and PIRT (phenomena identification ranking table) to represent phenomena characteristics of SMRs through fundamental tests, and separate and integral effect tests. The session will discuss the status of demonstration and development with their own national SMR drivers, and the identification and direction of design, licensing and construction. Through this panel session, international collaborations may be promoted to develop V&V experiments for SMR demonstration and development in a way of mutual benefits.
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Contact Person: Stephen M. Bajorek (United States Nuclear Regulatory Commission, United States)
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Program:
Panel Session - 07 Thermal-hydraulic and Fuel Coupling Analysis for Reactor Safety Evaluation
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Date & Time: September 4 (Thu), 10:20-11:50
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Organizer(s):
- Hyochan Kim (Korea Atomic Energy Research Institute, Korea, Republic of)
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Panelists:
- Jinzhao Zhang (Tractebel, Belgium)
- Pierre Ruyer (Autorité de Sûreté Nucléaire et de Radioprotection, France)
- Joosuk Lee (Korea Institute of Nuclear Safety, Korea, Republic of)
- Tongsoo Choi (KEPCO Nuclear Fuel, Korea, Republic of)
- Hyochan Kim (Korea Atomic Energy Research Institute, Korea, Republic of)
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Abstract
In this panel, a presentation of recent research trends regarding thermal-hydraulic and fuel coupling analysis will be made by each panelist, followed by a discussion of these trends by all panelists. The panel discussion focuses on the impact of fuel behaviours, including ballooning and relocation, on the blockage ratio of channels and local heating in accident conditions. The behaviours of thermal hydraulics are influenced by the blockage ratio and local heating. In particular, to take into account high burnup fuel behaviors including FFRD (Fuel fragmentation, relocation and dispersal) for the safety analysis, the proper coupling methodology need to be applied. It is anticipated that the panel discussion will facilitate the comprehension of the interactive phenomenon and the coupled analysis among the panel.
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Contact Person: Hyochan Kim (Korea Atomic Energy Research Institute, Korea, Republic of)
Panel Session - 08 A Life and Legacy in the Thermalhydraulics of CHF and Post Dryout
– In Memoriam of Dr. Dionysius (Dé) Groeneveld
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Date & Time: September 4 (Thu), 10:20-11:50
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Venue: Session Room 1 - #205 (2F)
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Organizer(s):
- Andrew Christopher Morreale (Canadian Nuclear Laboratories, Canada)
- David Novog (McMaster University, Canada)
- Jun Yang (Canadian Nuclear Laboratories, Canada)
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Moderator(s): Andrew Christopher Morreale (Canadian Nuclear Laboratories, Canada)
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Panelists:
- TBA
- Jun Yang (Canadian Nuclear Laboratories, Canada)
- Robert Bowden (Canadian Nuclear Laboratories, Canada)
- Sun-Kyu Yang (Canadian Nuclear Laboratories, Canada)
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Abstract
The topic of the thermalhydraulics of Critical Heat Flux and post-dryout is central to nuclear reactor safety and its research spans many decades of analysis and experiments. This session is held in Memoriam of Dr. Dionysius (Dé) Groeneveld, whose lifelong contribution to the nuclear industry covers all aspects of thermal hydraulics especially focused on CHF and post-dryout. Most known for his contributions to the CHF look-up table, De contributed a wealth of knowledge and developed dedicated methods to predict CHF and PDO, which have become essential for CANDU and PWR/BWR reactor design and safety analysis, and ubiquitous throughout the nuclear industry.
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Contact Person: Andrew Christopher Morreale (Canadian Nuclear Laboratories, Canada)