Scope & Topics

About Workshop

The CFD4NRS workshop (WS) was launched to establish a forum where numerical analysts, modelers, and experimentalists can exchange information on the application of Computational Fluid Dynamics (CFD) for Nuclear Power Plant (NPP) safety and advanced reactor issues.

Following the CFD4NRS WS held in Garching, Germany (September 2006), Grenoble, France (September 2008), Washington D.C., U.S. (September 2010), Daejeon, South Korea (September 2012), Zurich, Switzerland (September 2014), Cambridge, Massachusetts, U.S. – MIT (September 2016), Shanghai, China – Shanghai Jiao Tong University (September 2018), Online Forum, Saclay, France (November 2020), and College Station, Texas, U.S. – Texas A&M University (February 2023), this WA to be held at Mito City Civic Center in Ibaraki, Japan on December 10-12, 2025 (On-site only).

The objectives of this activity are:

• To provide an opportunity to exchange and share experiences and research results of the development and applications of CFD and computational multi-fluid dynamics (CMFD) tools for nuclear reactor safety (NRS) issues among international communities (academic scientists, researchers, engineers, regulators, research scholars and students) by organizing the 10th WS.
• The WS topics will include the CFD applications (single- or multi-phase) and the related experimental, instrumentation and data management issues.

This proposal follows TG activities on CFD application for the task group (TG) on application of CFD to NRS problems and conclusions of the CFD4NRS-9 WS held in Texas, USA (February, 2023). Guidelines by CFD-TG for the development, assessment and application of CFD and CMFD tools for NRS issues will be discussed. An updated state-of-the-art on specialized experiments will also be presented and compared to the needs for appropriate validation of the models.

Scope

This activity is related to the CFD application of advanced single- and two-phase flow models and numerical tools for simulating fluid dynamics and associated processes that may appear in reactor and containment vessel, including boiling and condensation, with fine space and time resolutions.

The CFD4NRS-10 WS will be devoted to the CFD applications for NRS issues and relevant experimental techniques with some emphasis on precise yet robust single-phase flow safety issues, extensions to two-phase flow issues, new measurement techniques for CFD-grade data, benchmark activities, and application of best practice guidelines (BPG) to simulations. The scope may include applications to flows in advanced reactor design including small modular reactors (SMR) and non-light water reactors, and utilization of new analysis methods under development. Possible data management issues for the CFD-grade data would be included.

The WS will also include report from the CFD benchmark activities on the on-going T-Junction: a synthesis of benchmark activities will be shared during the WS.

Topics

Accidents, Phenomena

• Nuclear Thermal Hydraulics (T/H)
  Code Development and Analysis
  • Design-bases Accident (DBA)
  • Design Extension Condition (DEC)
• Severe Accidents (SAs)
• Flows in Containment
  • Particle-laden Flows
  • Spray and Aerosol + Wall Interaction
• Pressurized Thermal Shock (PTS)
• Fluid-structure Interaction (FSI)
• Thermal Fatigue of Structure
• Fluid Phase Change
  • Condensation and Evaporation
• Boiling Heat Transfer
  • Departure from Nucleate Boiling (DNB)
  • Critical Heat Flux (CHF)

Methods, Applications

• CFD for Advanced Reactors including Small Modular Reactors (SMRs)
  • Unstable Passive System Flows
• Reduced Order Models
• Multiscale CFD
• Multiphase CFD
• Multiphysics CFD
• Coupling with System Codes
• CFD Open Source Codes
• Machine Learning (ML) and Artificial Intelligence (AI)
• Verification and Validation (V&V)
• Uncertainty Quantification (UQ)
• Benchmarking
  • DNS - CFD - Experiments
• CFD Best Practice Guidelines (BPGs)