PIV measurements for VVER pressurized water reactor rod bundle geometries including spacer grids for CFD model validations

Orosz, G.I. ✉ [Orosz, Gergely Imre (fizikai tudományok), szerző] Nukleáris Technikai Intézet (BME / TTK); Kacz, D. [Kacz, Dániel (nukleáris technika), szerző] Nukleáris Technikai Intézet (BME / TTK); Magyar, B. [Magyar, Boglárka (Energetika), szerző] Nukleáris Technika Tanszék (BME / TTK / NTI); Aszódi, A. [Aszódi, Attila (Energetika, atome...), szerző] Nukleáris Technikai Intézet (BME / TTK)

Angol nyelvű Szakcikk (Folyóiratcikk) Tudományos
Megjelent: NUCLEAR ENGINEERING AND DESIGN 0029-5493 1872-759X 419 Paper: 112938 , 23 p. 2024
  • SJR Scopus - Mechanical Engineering: Q1
A PIV (Particle Image Velocimetry) test facility called PIROUETTE (PIv ROd bUndlE Test faciliTy at bmE) has been built at BME (Budapest University of Technology and Economics) NTI (Institute of Nuclear Techniques). The facility is capable of investigating of flow processes under isothermal conditions with different type triangular lattice seven-rod bundles. The currently investigated rod bundle is featuring spacer grids and hydraulic conditions related to the VVER-1000 and VVER-1200 fuel assemblies. This small bundle of 7 rods is a geometrically accurate representation of a piece of the real reactor's fuel bundle, including the spacer grids. These spacer grids were 3D printed from a special type of plastic for the PIV experiments in order to reproduce the real geometry inside the assemblies as accurately as possible. The effect of the spacer grids with vanes (which are located on the spacer grid belt section) was investigated using different test grid configurations. The measurements aimed to capture high resolution flow fields inside the rod bundle with MIR (Matching Index of Refraction), in order to enable the flow measurements even within the bundle, where usually the flow field is not visible. For this purpose, the geometry was manufactured using special transparent materials. The detailed, high resolution experimental data could be used for CFD (Computational Fluid Dynamics) benchmarking and code validation, and therefore can serve the further safe and reliable operation of these reactors. The results include velocity field, velocity standard deviations (RMS), Reynolds stress and turbulent kinetic energy distributions extracted from the measured data. The attachments include the 3D model of the experimental geometry, measured velocity distributions and other parameters along various monitor lines. © 2024 The Author(s)
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2024-05-19 22:57