Pregled bibliografske jedinice broj: 354296
Analysis of Small Break LOCA During Mode 3 and Mode 4 Operation for NPP Krško
Analysis of Small Break LOCA During Mode 3 and Mode 4 Operation for NPP Krško // Proceedings of the International Conference Nuclear Energy for New Europe 2007 / Jenčič, Igor ; Lenošek, Melita (ur.).
Ljubljana: Nuclear Society of Slovenia, 2007. str. 215.1-215.8 (poster, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
CROSBI ID: 354296 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Analysis of Small Break LOCA During Mode 3 and Mode 4 Operation for NPP Krško
Autori
Šadek, Siniša ; Špalj, Srđan ; Bajs, Tomislav
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni
Izvornik
Proceedings of the International Conference Nuclear Energy for New Europe 2007
/ Jenčič, Igor ; Lenošek, Melita - Ljubljana : Nuclear Society of Slovenia, 2007, 215.1-215.8
ISBN
978-961-6207-28-7
Skup
International Conference Nuclear Energy for New Europe 2007
Mjesto i datum
Portorož, Slovenija, 10.09.2007. - 13.09.2007
Vrsta sudjelovanja
Poster
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
Small break LOCA; NPP; RELAP5
Sažetak
Small break loss of coolant accident (SB LOCA) analysis using RELAP5/Mod3.3 computer code during NPP Krško operation in shutdown modes (Mode 3 and Mode 4) was done in order to test the performance of the emergency core cooling system (ECCS) to mitigate such an event. ECCS is normally tested against a large break LOCA occurring at full power conditions because much higher core heat generation rates exist during full power operation. Nevertheless, ECCS system should provide protection in all modes of operation. Probability of a large break LOCA occurrence during Mode 3 and Mode 4 operation is very low, therefore only the analysis of the small break LOCA (break equivalent to that of six inch diameter) in the cold leg was performed. During Mode 3 or Mode 4 operation, the normal alignment of ECCS equipment is different than during the power operation. Accumulators are isolated and the automatic safety injection signal on low pressurizer pressure is blocked. Therefore, in these modes of operation, the operator action is required to mitigate the consequences of a LOCA event. The objective of the analyses was to demonstrate that the consequences of LOCA would be mitigated and the limits of 10CFR50.46 would not be exceeded if there was a timely operator action to initiate safety injection flow.
Izvorni jezik
Engleski
Znanstvena područja
Elektrotehnika
POVEZANOST RADA
Projekti:
036-0361590-1589 - Nuklearne elektrane za održivu proizvodnju električne energije (Feretić, Danilo, MZO ) ( CroRIS)
Ustanove:
Fakultet elektrotehnike i računarstva, Zagreb
