diplomsko delo
Anže Plankar (Author), Marko Čepin (Mentor)

Abstract

Jedrske elektrarne predstavljajo enega izmed ključnih virov električne energije v sodobnem energetskem sistemu, pri čemer so tlačnovodni reaktorji (PWR – Pressurized Water Reactor) najpogosteje uporabljena tehnologija. Njihovo delovanje temelji na jedrski cepitvi goriva, kjer se toplota iz primarnega kroga preko uparjalnikov prenese na sekundarni krog. Para, ustvarjena v sekundarnem krogu, poganja turbino z električnim generatorjem in tako proizvaja električno energijo. Diplomska naloga obravnava posledice zloma glavnega parovoda v tlačnovodni elektrarni z dvema hladilnima zankama, ki je primerljiva z jedrsko elektrarno Krško (NEK). Analiza je bila izvedena s pomočjo simulacijskega programa PCTRAN, ki omogoča natančno modeliranje obratovanja elektrarne ter odzivov njenih varnostnih sistemov. Preučena sta bila scenarija zloma parovoda z odprtinama velikosti 200 cm² in 300 cm² na eni od hladilnih zank. Rezultati simulacij kažejo, da se v obeh primerih hitro sprožijo ključni varnostni sistemi, med katerimi sta samodejna zaustavitev reaktorja (SCRAM) ter visokotlačni sistem za varnostno vbrizgavanje hladilne vode (HPIS). Ti sistemi uspešno preprečijo pregrevanje reaktorske sredice in ohranjajo delovanje sistema znotraj varnostno sprejemljivih mej. Izsledki te naloge prispevajo k boljšemu razumevanju dinamičnega odziva elektrarne ob tovrstnih nezgodah ter poudarjajo pomembnost učinkovitega delovanja varnostnih sistemov za zagotavljanje jedrske varnosti.

Keywords

jedrska elektrarna;varnostni sistemi;simulator;lom parovoda;hitra zaustavitev reaktorja;univerzitetni študij;Elektrotehnika;diplomske naloge;

Data

Language: Slovenian
Year of publishing:
Typology: 2.11 - Undergraduate Thesis
Organization: UL FE - Faculty of Electrical Engineering
Publisher: [A. Plankar]
UDC: 621.3(043.2)(0.034.2)
COBISS: 244777475 Link will open in a new window
Views: 118
Downloads: 35
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Other data

Secondary language: English
Secondary title: Analysis of a steam line break in a nuclear power plant with pressurized water reactor
Secondary abstract: Nuclear power plants represent one of the key sources of electricity in modern energy systems, with Pressurized Water Reactors (PWR) being the most common reactor technology in use. Their operation is based on the nuclear fission of fuel, wherein heat from the primary loop transfers through steam generators to the secondary loop. The resulting steam in the secondary loop drives a turbine connected to an electrical generator, producing electricity. This thesis examines the consequences of a main steam line break accident in a two-loop pressurized water reactor comparable to the Krško Nuclear Power Plant. The analysis was performed using the PCTRAN simulation software, enabling accurate modeling of plant operations and the response of safety systems. Two scenarios involving steam line breaks of 200 cm² and 300 cm² openings on one cooling loop were studied. Simulation results indicate that, in both scenarios, key safety systems, such as automatic reactor shutdown (SCRAM) and high-pressure injection system (HPIS), activate rapidly. These systems effectively prevent reactor core overheating and maintain system parameters within acceptable safety limits. The findings contribute to a better understanding of the dynamic response of a nuclear plant under such accident conditions and emphasize the importance of reliable safety systems for ensuring nuclear safety.
Secondary keywords: nuclear power plant;safety systems;simulator;steam line break;SCRAM;
Type (COBISS): Bachelor thesis/paper
Study programme: 1000313
Thesis comment: Univ. v Ljubljani, Fak. za elektrotehniko
Pages: 1 spletni vir (1 datoteka PDF (XX, 50 str.))
ID: 26802244