Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS), Shanghai, PR China, 4.9.2018 – 6.9.2018

The last two decades have witnessed an increasing use of three dimensional (3D) CFD and CMFD simulation techniques in nuclear reactor technology, in recognition of the fact that a number of important thermal-hydraulic phenomena cannot be predicted to the required accuracy and spatial resolution using traditional one-dimensional system codes. Requirements for validation of models used in CFD codes with the results of appropriate experiments prompted a joint OECD/NEA and IAEA initiative to form groups of experts with the specific task of addressing the maturity of CFD codes for NPP applications. Computational Fluid Dynamics for Nuclear Reactor Safety (CFD4NRS) workshop are intended to:

1. Set down Best Practice Guidelines for the use of CFD simulation techniques.
2. To document the validation database on which the level of maturity of CFD codes may be judged.
3. To catalogue the extensions needed to current CFD codes to enable them to perform trustworthy multi-phase simulations.
4. Review the methods for uncertainty quantification of CFD.

This was already seventh CFD4NRS workshop and was hosted by the Shanghai Jiao Tong University in PR China from 4 to 6 September 2018. Experimentalists and nuclear safety researchers using CFD codes in various applications of nuclear power plants exchanged their views on improving the experiments and validating CFD programs. Various authors presented their work in the fields of single-phase and multi-phase heat transfer, free-surface flows, condensation and turbulent mixing. The topics discussed refer to security problems in nuclear power plants such as pressurized thermal shock, critical heat flux, pool heat exchangers, spent fuel pool issues, boron dilution, hydrogen distribution in containments, design optimization...

The seventh version of the workshop was attended by Rok Krpan, a member of the Reactor Engineering Division of Jožef Stefan Institute.