Fluid mixing and flow distribution in the reactor circuit (FLOMIX-R)


Fluid mixing and flow distribution in the reactor circuit (FLOMIX-R)

Rohde, U.; Weiss, F.-P.; Karlsson, R.; Hemström, B.; Lillington, J.; Scheuerer, M.; Tuomisto, H.; Toppila, T.; Dury, T.; Cvan, M.; Muehlbauer;, P.; Toth, I.; Elter, J.; Bezrukov, Y.

The project aims at describing the mixing phenomena relevant for both safety analysis, particularly in steam line break and boron dilution scenarios, and mixing phenomena of interest for economical operation and the structural integrity. Measurement data from a set of mixing experiments, gained by using advanced measurement techniques with enhanced resolution in time and space help to improve the basic understanding of turbulent mixing and to provide data for Computational Fluid Dynamics (CFD) code validation. Slug mixing tests simulating the start-up of the first main circulation pump are performed with two 1:5 scaled facilities: The Rossendorf coolant mixing model ROCOM and the VATTENFALL test facility, modelling a German Konvoi type and a Westinghouse type three-loop PWR, respectively. Additional data on slug mixing in a VVER-1000 type reactor gained at a 1:5 scaled metal mock-up at EDO Gidropress are provided. Experimental results on mixing of fluids with density differences obtained at ROCOM and the FORTUM PTS test facility are made available.
Concerning mixing phenomena of interest for operational issues and thermal fatigue, flow distribution data available from commissioning tests (Sizewell-B for PWRs, Loviisa and Paks for VVERs) are used together with the data from the ROCOM facility as a basis for the flow distribution studies. The test matrix on flow distribution and steady state mixing performed at ROCOM comprises experiments with various combinations of running pumps and various mass flow rates in the working loops.
Computational fluid dynamics calculations are accomplished for selected experiments with two different CFD codes (CFX-5, FLUENT). The applicability of various turbulence modelling techniques is studied for transient and steady state flow. Best practice guidelines (BPG) are referenced in all CFD work when choosing computational grid, time step, turbulence models, modelling of internal geometry, boundary conditions, numerical schemes and convergence criteria. The strategy of code validation based on the BPG and a matrix of CFD code validation calculations have been elaborated. The computational grid generation for the test facilities and first calculations on the benchmark tests have been performed.

Keywords: turbulent mixing; boron dilution; test facility; computational fluid dynamics; code validation; nuclear reactor; safety analysis

  • Lecture (Conference)
    Symposium FISA-2003 - EU research in reactor safety, Luxembourg, November 10-13, 2003; Pre-proceedings pp. 198-204
  • Contribution to proceedings
    Symposium FISA-2003 - EU research in reactor safety, Luxembourg, November 10-13, 2003; Pre-proceedings pp. 198-204

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