Experiments and CFD Code Application to Nuclear Reactor Safety (XCFD4NRS): Workshop Proceedings

NEA/CSNI/R(2009)12
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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 coolant system to be better described. The Committee on the Safety of Nuclear Installations (CSNI) has in recent years conducted important activity in the CFD area. This activity has been carried out within the scope of the CSNI working group on the analysis and management of accidents (WGAMA), and has mainly focused on the  formulation of user guidelines and on the assessment and verification of CFD codes. It is in this WGAMA framework that a first workshop CFD4NRS was organised and held in Garching, Germany in 2006.

Following the CFD4NRS workshop, this XCFD4NRS workshop was intended to extend the forum created for numerical analysts and experimentalists to exchange information in the field of nuclear reactor safety (NRS) related activities relevant to CFD validation, but this time with more emphasis placed on new experimental techniques and two-phase CFD applications.

The purpose of the workshop was to provide a forum for numerical analysts and experimentalists to exchange information in the field of NRS-related activities relevant to CFD validation, with the objective of providing input to WGAMA CFD experts to create a practical, state-of-the-art, web-based assessment matrix on the use of CFD for NRS applications.