IAEA CRP benchmark of ROCOM PTS test case for the use of CFD in reactor design using ANSYS CFX

IAEA CRP benchmark of ROCOM PTS test case for the use of CFD in reactor design using ANSYS CFX

Höhne, T.

Over the last 15 years, considerable effort has been expended in assembling the available information on the use of CFD in the nuclear reactor safety field. Typical application areas here are heterogeneous mixing and heat transfer in complex geometries, buoyancy-induced natural and mixed convection, etc., with specific reference to NRS accident scenarios such as Pressurized Thermal Shock (PTS), boron dilution, hydrogen build-up in containments, thermal fatigue and thermal striping issues, etc. The development, verification and validation of CFD codes in respect to NPP design necessitates further work on the complex physical modelling processes involved, and on the development of efficient numerical schemes needed to solve the basic equations. Therefore, a set of ROCOM CFD-grade test data were made available to set up an IAEA benchmark, relating to Pressurized Thermal Shock (PTS) scenarios. The benchmark deals with the injection of the relatively cold Emergency Core Cooling (ECC) water which can induce buoyancy-driven stratification. Data obtained from the PTS experiment were compared with predictions obtained from the CFD software ANSYS CFX.

The results of the experiment and of the numerical calculations show that mixing is dominated by buoyancy effects: at higher mass flow rates (close to nominal conditions) the injected slug propagates in the circumferential direction around the core barrel. Buoyancy effects reduce this propagation. The ECC water falls in an almost vertical path and reaches the lower down-comer sen¬sor directly below the inlet nozzle. Therefore, density effects play an important role during natural convection with ECC injection in PWRs. CFD was able to predict well the observed flow patterns and mixing phenomena.


  • Lecture (Conference)
    Fourth Research Coordination Meeting on the Application of Computational Fluid Dynamics Codes for Nuclear Power Plant Design, 08.11.2017, Wien, Österreich

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Publ.-Id: 26114