zaključna naloga
Jakob Justin (Author), Boštjan Končar (Mentor), Martin Draksler (Co-mentor)

Abstract

Pri hipotetični nezgodi izgube hlajenja v fuzijskem reaktorju, zaradi giljotinskega zloma cevi hladilnega sistema izven vakuumske posode, predpostavimo takojšnjo izgubo hlajenja oplodnih oblog v enem sektorju tokamaka. Zaradi aktivacije materialov moramo zaostalo toploto iz reaktorja odvajati tudi po zaustavitvi. V ta namen po izgubi hlajenja v vakuumsko posodo vpihnemo suh, hladen zrak. Ko se vzpostavi naravna konvekcija, kroženje zraka med vročimi in hladnimi deli reaktorske posode zagotovi pasiven mehanizem prenosa toplote med vročimi komponentami ter hladnimi okoliškimi površinami. Z uporabo programa za računsko dinamiko tekočin ANSYS Fluent smo izvedli numerično analizo segrevanja prizadetega segmenta oplodnih oblog v DEMO reaktorju. Uporabili smo sklopljen model vezanega prenosa toplote v tekočini in trdnini z upoštevanjem toplotnega sevanja. Pokazali smo, da z naravno konvekcijo vpihanega zraka zagotavljamo zadostno hlajenje oplodnih oblog, katerih temperatura sicer sprva nekoliko naraste, nato pa se sistem začne ohlajati.

Keywords

fuzijski reaktorji;reaktor DEMO;nezgode;izguba hlajenja;oplodna obloga;naravna konvekcija;računska dinamika tekočin;

Data

Language: Slovenian
Year of publishing:
Typology: 2.11 - Undergraduate Thesis
Organization: UL FMF - Faculty of Mathematics and Physics
Publisher: [J. Justin]
UDC: 532.5
COBISS: 77575427 Link will open in a new window
Views: 210
Downloads: 30
Average score: 0 (0 votes)
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Other data

Secondary language: English
Secondary title: Numerical simulation of a hypothetical loss of coolant accident in a fusion reactor
Secondary abstract: In a hypothetical loss of coolant accident, a guillotine break of a coolant line occurs outside the vacuum vessel, that causes instantaneous loss of cooling of breeding blankets in one sector of the tokamak. Due to the material activation, residual heat must be dissipated from the reactor even after the reactor shutdown. With additional cooling functions, potential damage to the in vessel components of the reactor due to overheating can be prevented. For this purpose, dry air is injected into the vacuum vessel to facilitate convective cooling of the affected components. A numerical analysis of the cooling of the affected sector of the DEMO reactor has been performed, using the ANSYS Fluent computational fluid dynamics software. A conjugate heat transfer model for fluids and solids was used, with the inclusion of thermal radiation. The analysis showed that natural convection of the air provides sufficient cooling of the breeding blankets. The temperature of the blankets initially rises, then the system starts to cool down.
Secondary keywords: fusion power plant;reactor DEMO;accidents;loss of coolant;breeding blanket;natural convection;computational fluid dynamics;
Type (COBISS): Final paper
Study programme: 0
Thesis comment: Univ. v Ljubljani, Fak. za matematiko in fiziko, Oddelek za fiziko
Pages: 22 f.
ID: 13525391