Paper Invitation
NURETH-21 invites paper submissions to share the latest research findings in nuclear thermal hydraulics on the following technical topics.
Selected papers will be presented at NURETH-21 as an oral session or poster.
For any inquires related to NURETH-21, please contact at paper@nureth-21.org.
Important Dates
Abstract submission deadline
October 25, 2024
Author notification of acceptance
November 15, 2024
Full paper submission deadline
January 31, 2025
Full paper review notification
March 17, 2025
Revised paper submission deadline
April 15, 2025
Final paper submission deadline
May 15, 2025
Technical Tracks
1. Fundamental Thermal Hydraulics
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General Fundamental Thermal Hydraulics
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Single Phase Thermal Hydraulics
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Two-Phase Flow
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Boiling and Condensation
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Critical Heat Flux (CHF) and DNB
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Core and Sub-Channel Thermal Hydraulics
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Natural Circulation
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Thermal Hydraulic Scaling
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Instabilities and Special Thermal Hydraulic Phenomena
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Turbulence
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Adv. Modelling - IAT, Droplets, etc.
2. Computational Thermal Hydraulics
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Computational Fluid Dynamics
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Computational Multi-Fluid Dynamics
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Sub-channel Analysis
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System Code Analysis
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Multi-field Analysis and Modelling
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High-fidelity Coupled Analysis
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DNS and LES
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Uncertainty Quantification and Best Practice Guidelines for Analysis
3. SET & IET
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Measurement Techniques and Visualization
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SET & IET (1): LWR
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SET & IET (2): Non-LWR
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CFD-grade Tests
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Experiments and Databases for Validation
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Rod Bundle Experiments
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CHF for SMR and Accident Tolerant Fuel
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Uncertainty Quantification and Best Practice Guidelines for Experiments
4. Water-cooled Reactor Thermal Hydraulics
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WCR Operation and Safety - PWR & VVER
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WCR Operation and Safety - HWR
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WCR Transient & Accident Analysis
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ALWR Thermal Hydraulics & Safety
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ATF & LEU+ Issues
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LTO and Flexible Operation
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BEPU - Methodology & Analysis
5. Severe Accident
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Severe Accident Management and Mitigation in PWR
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In-Vessel Corium Behavior and Cooliability
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Ex-Vessel Corium Behavior and Cooliability
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FCI and Containment Integrity
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Hydrogen Issues & Management
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Fission Products Behavior and Reduction
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Passive Autocatalytic Recombiners
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Severe Accident in Advanced Reactor
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Severe Accident in PHWR
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Severe Accident Uncertainty Analysis
6. Advanced Reactor Thermal Hydraulics and Safety
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Water-cooled SMRs
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Non-water-cooled SMRs
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Micro-Reactors
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Non-electricity Generation Applications
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Test/Research Reactors
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Molten Salt Reactors
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Gas-Cooled Reactors
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Liquid Metal Reactors: SFR, LFR
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Other Advanced Reactors - SCWR
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Thermal Hydraulics in Fusion Reactors
7. Digital Technologies for Thermal Hydraulics
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AI Application to Thermal Hydraulics
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AI Application to Operation and Safety
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Reduced Order Modelling (ROM) for Nuclear Thermal Hydraulics
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Virtual Reactor Design
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Monitoring and Diagnosis of Thermal Hydraulics
8. Special Topics
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Thermal Hydraulics in Waste Management
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Thermal Hydraulics in H2 Production/Transport
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Multi-scale Multi-Physics
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Coolant Chemistry
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Microchannel Thermal Hydraulics
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Space Applications
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Marine Applications
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Fluid-Structure Interaction
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Post-Fukushima Safety Issues
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Reliability of Passive Systems
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Emerging Thermal Hydraulics & Safety Issues
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Thermal Hydraulics in Thermal Storage System
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Integrated Energy Systems
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Risk-informed Safety Assessment
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Multi-Organizational Cooperative Programs
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International Cooperative Programs
9. Panel/Forum Sessions
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Licensing Approaches on BEPU for Passive System
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Thermal Hydraulics Issues on HALEU Fuels
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LWR Fuel Reliability
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MSR Forum
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Water-cooled SMR
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Thermal Hydraulics Challenges and Opportunities in Operating Reactors
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Deployment of Advanced Reactors
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Safety and Thermal-Hydraulics in Fukushima Decommissioning