Assessment of CFD Codes for Nuclear Reactor Safety Problems – Revision 2

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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, held in Aix-en-Provence, France on 15-16 May 2002, and a follow-up meeting on the use of Computational Fluid Dynamics (CFD) codes for safety analysis of reactor systems including containment, which took place in Pisa on 11-14 November 2002, a CSNI action plan was drawn up which resulted in the creation of three writing groups, with mandates to perform the following tasks: provide a set of guidelines for the application of CFD to NRS problems; evaluate the existing CFD assessment bases, and identify gaps that need to be filled; summarise the extensions needed to CFD codes for application to two-phase NRS problems.