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Modeliranje nove jedrske elektrarne tipa AP1000
ID GERJEVIČ, GREGA (Author), ID Čepin, Marko (Mentor) More about this mentor... This link opens in a new window

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MD5: C8A191DB9D906A1F5A5B432784E26017
PID: 20.500.12556/rul/5ad4021e-d8e9-415d-81e5-a2daeab1fde3

Abstract
Diplomsko delo zajema primerjavo rezultatov simulacije male izlivne nezgode s programskim orodjem Advanced PWR simulator z rezultati, ki jih je opravilo podjetje Westinghouse v testnem objektu APEX-1000. V prvem delu diplomskega dela sta opisana primarni in sekundarni sistem, ki se bistveno ne razlikujeta od sistemov ostalih jedrskih elektrarn. Nato sledi opis pasivnih varnostnih sistemov, po katerih je AP1000 znana. Sledi splošen opis izlivne nezgode, simulacijskega orodja in potek simulacije. V zadnjem delu pa so predstavljeni rezultati simulacije, njihova primerjava in komentar. Rezultati kažejo na to, da simulacijsko orodje Advanced PWR simulator ni primerno za podrobnejšo analizo projektnih nezgod v jedrskih elektrarnah ampak lahko služi predvsem kot orodje za boljšo predstavo delovanja sistemov v jedrskih elektrarnah.

Language:Slovenian
Keywords:jedrska elektrarna AP1000, pasivni varnostni sistemi, PXS, mala izlivna nezgoda, programsko orodje Advanced PWR simulator, testni objekt APEX-1000
Work type:Undergraduate thesis
Organization:FE - Faculty of Electrical Engineering
Year:2015
PID:20.500.12556/RUL-73404 This link opens in a new window
Publication date in RUL:11.11.2015
Views:2575
Downloads:859
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Secondary language

Language:English
Title:Modelling of a new nuclear power plant AP1000
Abstract:
The diploma thesis contains comparison of the simulation results small break loss of coolant accident with Advanced PWR simulator software and the results made by Westinghouse in the test facility APEX-1000. The first part of the diploma thesis contains description of the primary and secondary system, which do not differ significantly from the systems of other nuclear power plants. This is followed by a description of the passive safety systems under which the AP1000 is known. Below, there is a general description of loss of coolant accident, Advanced PWR simulator software and conduct simulation. The last part presents the results of simulations, their comparison and comment. The results show that the simulation tool Advanced PWR simulator is not suitable for a more detailed analysis of design accidents in nuclear power plants but can serve mainly as a tool to improve the understanding of the performance operation of the systems in nuclear power plants.

Keywords:Advanced passive PWR AP1000, passive safety systems, PXS, small break loss of coolant accident, Advanced PWR simulator software, test facility APEX-1000

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