Pregled bibliografske jedinice broj: 458803
Upgrade to NPP Krško Internal Flooding PSA
Upgrade to NPP Krško Internal Flooding PSA // Proceedings of the International Conference Nuclear Energy for New Europe 2009 / Cizelj, Leon ; Končar, Boštjan ; Leskovar, Matjaž (ur.).
Ljubljana: Nuclear Society of Slovenia, 2009. str. 308.1-308.8 (predavanje, međunarodna recenzija, cjeloviti rad (in extenso), stručni)
CROSBI ID: 458803 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Upgrade to NPP Krško Internal Flooding PSA
Autori
Vrbanić, Ivan ; Bašić, Ivica ; Prosen, Rudolf
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), stručni
Izvornik
Proceedings of the International Conference Nuclear Energy for New Europe 2009
/ Cizelj, Leon ; Končar, Boštjan ; Leskovar, Matjaž - Ljubljana : Nuclear Society of Slovenia, 2009, 308.1-308.8
ISBN
978-961-6207-30-0
Skup
International Conference Nuclear Energy for New Europe 2009
Mjesto i datum
Bled, Slovenija, 14.09.2009. - 17.09.2009
Vrsta sudjelovanja
Predavanje
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
NPP Krško; Internal Flooding PSA
Sažetak
The existing internal flooding probabilistic safety analysis (PSA) study of Krško NPP was upgraded in response to the Krsko Periodic Safety Review (PSR) issues concerning the screening criteria for internal floods, residual risk from screened out areas and propagation of scenarios to plant damage states and Level 2. The area screening process was revisited in order to cover also the areas with relevant risk potential, although without automatic reactor trip equipment, which may have been screened out in the original study. Through the screening process, the residual core damage frequency (CDF) from screened out areas was systematically estimated in order to demonstrate that its combined value is acceptably low as compared to the total estimated internal flooding CDF. In the next step, the internal flooding PSA model was extended to Level 2 in order to address the corresponding PSR issue. All Level 1 core damage sequences from the internal flooding event trees in the PSA model were extended to Level 2. Frequencies of release categories were quantified. The plant area screening process was repeated at Level 2 in a manner equivalent to the screening at Level 1. Residual Level 2 risk was estimated in terms of large early release frequency (LERF). The paper describes the overall process of upgrading the internal flooding PSA study and model, and presents its results.
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