The 9^th edition of the Computational Fluid Dynamics for Nuclear Reactor Safety workshop was hosted by Texas A&M University on 20-22 February 2023. 

Following recommendations made at an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) codes to nuclear reactor safety (NRS) problems, h...

Following recommendations made at an “Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety (NRS) Problems”,...

In May 2002, an “Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety Problems” was held in Aix-en-Provence...

In May 2002, an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) Codes to nuclear reactor safety problems was held in Aix-en-Provence, ...

Following the CFD4NRS workshops held in Garching, Germany (September 2006), Grenoble, France (September 2008) and Washington D.C., USA (September 2010), this workshop, held in Daejeon, Korea on 10-12...

NEA Working Group on Analysis and Management of Accidents (WGAMA) initiated this activity focusing on computational fluid dynamics (CFD) in nuclear reactor safety (NRS).

The eighth instalment of the workshop on computational fluid dynamics for nuclear reactor safety (CFD4NRS-8) was organised by the Nuclear Energy Agency (NEA) Committee on the Safety of Nuclear Instal...

This report initially provides a brief overview of the main features of a PWR, BWR, CANDU and VVER reactors. It also provides an overview of the ex-vessel corium retention (core catcher) and a genera...

This Technical Opinion Paper (TOP) studies the emerging use of computational fluid dynamics (CFD) as an additional tool for the evaluation of safety cases implying thermal hydraulics. CFD allows a fi...

This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by the Writing Group 3 on the extension of CFD to two-phase flow safety problems, which was formed following the recommen...

This document is an extension of the NEA/SEN/SIN/AMA(2006)2 report produced by Writing Group 3 on the extension of computational fluid dynamics (CFD) to two-phase flow safety problems. Writing Group ...

The main objective of ISP-47 was to assess the capabilities of lumped parameter (LP) and computational fluid dynamics (CFD) codes in the area of containment thermal-hydraulics. Following the recommen...

NEA Working Group on the Analysis and Management of Accidents (WGAMA) held its annual meeting, hosted by the CEA and atttended by nearly 90 delegates from 19 member countries, along with representati...

The OECD/SETH-2 project was carried out during the period 2007-2010 under the auspices of the Nuclear Energy Agency (NEA) and with support provided by the Czech Republic, Finland, France, Germany, Ja...

The NEA Working Group on the Analysis and Management of Accidents convened for its annual meeting to discuss ongoing work related to accident strategy and management.

Prevention, mitigation and management of potential accidents in nuclear power plants

The OECD Nuclear Energy Agency developed an initiative to form writing groups of experts with the specific task of assessing the maturity of computational fluid dynamics (CFD) codes for nuclear reaco...

The OECD/NEA-KAERI MATiS-H benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict important turbulence parameters downstream of a generic ...

The OECD/NEA-Vattenfall T-Junction Benchmark was initiated to test the ability of state-of-the-art computational fluid dynamics (CFD) codes to predict the important parameters affecting high-cycle th...

When looking for a validation experiment for CFD application to reactor simulation for either design or safety studies, it appears that available data often suffer from a lack of local measurements, ...

Single-phase computational fluid dynamics (CFD) is used more and more for design and safety issues related to light-water reactor (LWR) thermal hydraulics. Over the past ten years, the Working Group ...

NEA CFD-Task Group members discussed ongoing activities at a meeting hosted on 11-12 July 2024.

This report provides the results of the fluid structure interaction (FSI) benchmark, which was developed and performed by the designer and engineering company OKBM as part of NEA and ROSATOM activiti...

Computational fluid dynamics (CFD) is to an increasing extent being adopted in nuclear reactor safety analyses as a tool that enables specific safety relevant phenomena occurring in the reactor coola...

The Workshop on Experimental Validation and Application of CFD and CMFD Codes to Nuclear Reactor Safety Issues, CFD4NRS-7 was the seventh in a series of workshops focusing on Computational Fluid Dyna...