31-07-2022: The next edition of CFD4NRS will take place at Texas A&M University, College Station, Texas, USA, in February 2023; and will be chaired by Pr. Yassin Hassan. See you there!

---> https://www.tamu.edu

.. and thanks a lot to all the participants and committee members of V-CFD4NRS8!

Mathieu Guingo

16-10-2020: REGISTRATIONS ARE NOW OPENED: Please use the dedicated website: https://www.azur-colloque.fr/DR04/inscription/inscription/180  (Registration fees amount to 108 euros)

9-7-20: IMPORTANT UPDATE: Due to the current sanitary situation, the 8th edition of CFD4NRS will be held entirely online. Stay safe !

After Zurich (2014), Boston (2016) and Shanghai (2018), the next edition of the OECD/NEA CFD4NRS (Computational Fluid Dynamics for Nuclear Reactor Safety) Workshop will take place online, from the 25th to the 27th November 2020.

As the 8^th edition of this workshop, it ambitions to be a forum during which numerical analysts and experimentalists can exchange new information on the application of CFD to nuclear power plants safety and design issues. Both new experimental data for CFD code validation, as well as state-of-the-art (single or multi-phase) CFD applications will be presented. Emphasis will be put on:

•  Experiments aiming at providing CFD-level validation data, which include local measurements (multi-sensor probes, laser-based techniques, etc.). This kind of communication should include detailed information on initial and boundary conditions, mandatory for the subsequent CFD simulations; as well as discussion on measurement uncertainties and error bound.

• Single-phase or multiphase CFD simulations with a significant focus on verification and validation, in connection with nuclear safety issues, which can include critical heat flux (CHF), pressurized thermal shock (PTS), pool heat exchangers, passive-systems design, advanced reactor design, boron dilution, thermal striping and fatigue, containment flows, etc. The respect of the current Best Practice Guidelines (for instance Mahaffy J. et al. “Best Practice Guidelines for the Use of CFD in Nuclear Reactor Safety Applications – Revision”, NEA/CSNI/R(2014)11, February 2015) for this kind of simulations will be severely scrutinized in the review process. Discussion of Uncertainty Quantification (UQ) is also highly encouraged.

Background image courtesy of Céline Caruyer and Nicolas Mérigoux, EDF