Pregled bibliografske jedinice broj: 44558
CORE-WIDE DNBR CALCULATION FOR NPP KRŠKO MSLB
CORE-WIDE DNBR CALCULATION FOR NPP KRŠKO MSLB // International Conference Nuclear Energy in Central Europe 2000 Proceedings / Mavko, Borut ; Cizelj, Leon ; Kovač, Marko (ur.).
Ljubljana: Nuclear Society of Slovenia, 2000. (poster, međunarodna recenzija, cjeloviti rad (in extenso), stručni)
CROSBI ID: 44558 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
CORE-WIDE DNBR CALCULATION FOR NPP KRŠKO MSLB
Autori
Jurković, Ines-Ana ; Grgić, Davor ; Debrecin, Nenad
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), stručni
Izvornik
International Conference Nuclear Energy in Central Europe 2000 Proceedings
/ Mavko, Borut ; Cizelj, Leon ; Kovač, Marko - Ljubljana : Nuclear Society of Slovenia, 2000
Skup
International Conference Nuclear Energy in Central Europe 2000
Mjesto i datum
Bled, Slovenija, 11.09.2000. - 14.09.2000
Vrsta sudjelovanja
Poster
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
DNBR; core; NPP Krško; MSLB
Sažetak
This paper presents the comparison between capabilities of coupled code (system code
RELAP5, 3-D neutronics code QUABOX/CUBBOX) with and without additional COBRA
core model in case of NPP Krško MSLB accident calculation. The differences in global
system parameters are small, even for reduced scram reactivity worth. Better spatial
resolution and accuracy are achievable with COBRA core model at the cost of increase in
CPU time for about factor two. The coupled system with COBRA addition is capable to
calculate core-wide DNBR distribution, both in steady state and in transient, using one
average coolant channel per fuel assembly. It is expected to see larger differences in codes
predictions and additional benefits of 3D COBRA core model usage and of core-wide DNBR
capability in case of HZP MSLB.
Izvorni jezik
Engleski
Znanstvena područja
Elektrotehnika