Pregled bibliografske jedinice broj: 458664
Analysis of OECD/CSNI ISP-42 Phase A PANDA Experiment Using RELAP5/mod3.3 and GOTHIC 7.2a Codes
Analysis of OECD/CSNI ISP-42 Phase A PANDA Experiment Using RELAP5/mod3.3 and GOTHIC 7.2a Codes // 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. 416.1-416.9 (predavanje, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
CROSBI ID: 458664 Za ispravke kontaktirajte CROSBI podršku putem web obrasca
Naslov
Analysis of OECD/CSNI ISP-42 Phase A PANDA Experiment Using RELAP5/mod3.3 and GOTHIC 7.2a Codes
Autori
Benčik, Vesna ; Debrecin, Nenad ; Grgić, Davor
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 2009
/ Cizelj, Leon ; Končar, Boštjan ; Leskovar, Matjaž - Ljubljana : Nuclear Society of Slovenia, 2009, 416.1-416.9
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
ISP-42; PANDA; RELAP; GOTHIC
Sažetak
The investigation of effectiveness of passive safety systems of recent Advanced Light Water Reactors (ALWR)s has gained an appreciable attention in the last decade. This was the main objective of the international research project TEPSS (Technology Enhancement of Passive Safety Systems) as well as OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) International Standard Problem (ISP)-42 test in PANDA (Passive Nachwärmeabfuhr und Druckabbau Test Anlage) facility. PANDA is a large-scale thermal-hydraulic test facility installed at the Paul Scherrer Institute (PSI) in Switzerland. Its primary goal is the simulation of passive containment for ALWRs. The OECD/CSNI ISP-42 test consists of six sequential phases (Phase A through F). The present work deals with the post-test calculation of the Phase A, including the break of the main steam line and the Passive Containment Cooling (PCC) System Start-Up. The calculation has been performed using stand-alone codes RELAP5/mod3.3 and GOTHIC 7.2a. The analysis was performed as preparatory phase for application of coupled RELAP5 + GOTHIC code for analysis of the same experiment. The intention is to see if there are any benefits in usage of the codes more suited for the coupled system-containment calculation in the situation where that is more important than in the current reactor systems. The comparison between RELAP5 and GOTHIC analysis has shown a good qualitative agreement for all the phases of the simulation and has provided good basis for application of the coupled code and for making decision where the modelling boundary between two codes should be placed.
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