magistrsko delo magistrskega študijskega programa II. stopnje Strojništvo
Patrik Tarfila (Author), Miroslav Halilovič (Mentor), Boštjan Končar (Co-mentor)

Abstract

Diverter fuzijskega reaktorja je med obratovanjem izpostavljen visokemu površinskemu toplotnemu toku zaradi energijskih delcev plazme. Za preizkušanje različnih konfiguracij diverterja bodo v Frascatiju v Italiji zgradili eksperimentalni fuzijski tokamak, ki bo omogočal postavitve različnih konfiguracij plazme in diverterja. V magistrskem delu smo analizirali toplotne obremenitve, napetosti in deformacije delov diverterja izpostavljenih plazemskemu toku. Zaradi visokih toplotnih obremenitev so pričakovane visoke napetosti in možnost prehoda iz elastičnega v plastično stanje posameznih nenosilnih komponent. Cilj naloge je bil napovedati pomike in napetosti v komponentah s pomočjo numeričnih simulacij, kot tudi vrednotiti napetosti v kritičnih prerezih na podlagi standardiziranih meril konstrukcijske zasnove komponent. Najprej smo pripravili geometrijo, izdelali mrežo za celotne in pomanjšane modele ter razvili računski model v programskih paketih ANSYS in ABAQUS. Nato smo izvedli termohidravlično analizo za pridobitev temperaturne porazdelitve, ki je služila kot vhodni robni pogoj toplotne obremenitve v termomehanski analizi. Ugotovili smo, da nosilne komponente zdržijo predvidene toplotne in mehanske obremenitve, kot tudi da se zaradi visokih temperatur pojavi tečenje materiala v nekaterih nenosilnih komponentah.

Keywords

magistrske naloge;tokamak DTT;diverterska enota;računalniška dinamika tekočin;metoda končnih elementov;termomehanska analiza;elasto-plastičnost;kriteriji SDC-IC;

Data

Language: Slovenian
Year of publishing:
Typology: 2.09 - Master's Thesis
Organization: UL FS - Faculty of Mechanical Engineering
Publisher: [P. Tarfila]
UDC: 532.5:519.6(043.2)
COBISS: 156534787 Link will open in a new window
Views: 13
Downloads: 5
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Other data

Secondary language: English
Secondary title: Thermo-hydraulic and thermo-mechanical numerical analyses of DTT divertor target
Secondary abstract: Divertor in a fusion reactor is exposed to a high surface heat flux during its operation due to plasma fluence. For testing the different divertor configurations, an experimental fusion tokamak will be built in Frascati in Italy, which will allow testing of different plasma scenarios and divertor configurations. In this master thesis thermal loads, stresses and deformations in plasma-facing divertor components have been analysed. High stresses are expected due to high thermal loads and also material yielding can occur in non-structural components. The main objective of this thesis is to predict displacements and stresses in the components using numerical simulations as well as validation of stresses in critical cross-sections with the use of standardized criteria of structural design of components. At first, the geometry was prepared, then the meshes for the whole and small models together with computational setup were created using the ANSYS and ABAQUS software. In the first part, the thermo-hydraulic simulations were performed to get temperature distribution, which were used as a temperature boundary condition in thermo-mechanical analysis. It was found, that structural components withstand the foreseen loads and also yielding occurred in some non-structural components.
Secondary keywords: master thesis;tokamak DTT;divertor unit;computational fluid dynamics;finite element method;thermo-mechanical analysis;elasto-plasticity;criteria SDC-IC;
Type (COBISS): Master's thesis/paper
Study programme: 0
Thesis comment: Univ. Ljubljana, Fak. za strojništvo
Pages: XXVIII, 79 str.
ID: 19356496