In 2022, the WPRS Expert Group on Thermal Hydraulics and Mechanics (EGTHM) mandated a new benchmark on high-temperature gas-cooled reactors (HTGR) using high-temperature test facility (HTTF) data an...

The aim of this second revision of the Best Practice Guidelines (BPG) is to provide guidance to the user of computational fluid dynamics (CFD) codes, both novice and experienced, in the field of nucl...

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...

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...

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...

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.

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...

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. 

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

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, ...

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...

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 ...

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 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...

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 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...