A témavezető neve:
Yamaji Bogdán - tanszéke: Institute of Nuclear Techniques - beosztása: Associate Professor - tudományos fokozata: PhD - email címe: yamaji@reak.bme.hu |
A doktori munka készítésénak helye és címe: Institute of Nuclear techniques 1111 Budapest, Műegyetem rkp. 9. |
A kidolgozandó feladat címe: Experimental modelling and investigation of fluid flow in hexagonal rod bundle geometries |
A téma rövid leírása, a megoldandó legfontosabb feladatok felsorolása: Particle Image Velocimetry (PIV) is a state-of-the-art non-intrusive optical flow measurement method based on the recording of the movement of flow-following particle images added to the liquid in the investigated domain. PIV is in use at BME Institute of Nuclear Techniques (NTI) since 2007, and has been applied for such investigations as coolant mixing, heat transfer of the fuel rod of the training Reactor or thermal-hydraulics characteristics of the MSFR molten salt reactor concept core. With the application of Matched Index of Refraction (MIR) method it is possible to investigate the flow field in complex geometries. By matching the refractive indices of the model material and the working fluid the flow domain behind a solid model part becomes visible for the optical method, thus allowing the measurement in geometries such as rod bundles. Most of the publications in the international literature focus on rectangular lattice geometries as these are common for fuel rod bundles applied in western pressurized water reactors (PWRs). However in case of VVER reactors and some Generation IV reactor types, for example the Allegro gas-cooled demonstrator fast reactor hexagonal lattice is applied. So far only a limited number of publications presented PIV measurement results of hexagonal lattice rod bundle PIV measurements. Main purpose of the work proposed here is to develop an appropriate experimental model of hexagonal fuel rod bundles that can be applied with PIV. The measurement data would lead to a deeper understanding of flow behaviour in such geometries, and would be invaluable for validating computational models and simulation results. Such an experimental model would be a new, state-of-the-art and unique facility even in terms of international comparison. One of the objectives of the PhD research is to deliver new CFD-grade experimental data, which would be applicable for the validation of CFD codes and models. The PhD candidate would perform the following tasks:
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A jelentkezővel szemben támasztott elvárások: Adequate knowledge of nuclear reactor thermal hydraulics and Computational Fluid Dynamics Basic knowledge of measurement techniques applied in thermal-hydraulics Affinity for using computational modelling tools, applying experimental methods Good level of English |
Nyilatkozat: A fenti munkahelyen a javasolt témában kutatás feltételei biztosítottak, a téma meghirdetését a munkahelyi vezető jóváhagyta. |
Budapesti Műszaki és Gazdaságtudományi Egyetem Természettudományi Kar |
1111 Budapest, Műegyetem rakpart 3. K épület I. em. 18. www.ttk.bme.hu |