Pregled bibliografske jedinice broj: 409714
QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code
QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code // Proceedings of the 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids / Čavlina, Nikola ; Pevec, Dubravko ; Bajs, Tomislav (ur.).
Zagreb: Hrvatsko nuklearno društvo, 2008. str. S5-66.1 (poster, međunarodna recenzija, cjeloviti rad (in extenso), znanstveni)
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Naslov
QUENCH-11 Experiment Analysis with RELAP5/SCDAPSIM Code
Autori
Šadek, Siniša ; Debrecin, Nenad ; Špalj, Srđan
Vrsta, podvrsta i kategorija rada
Radovi u zbornicima skupova, cjeloviti rad (in extenso), znanstveni
Izvornik
Proceedings of the 7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids
/ Čavlina, Nikola ; Pevec, Dubravko ; Bajs, Tomislav - Zagreb : Hrvatsko nuklearno društvo, 2008, S5-66.1
ISBN
978-953-55224-0-9
Skup
7th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids
Mjesto i datum
Dubrovnik, Hrvatska, 25.05.2008. - 29.05.2008
Vrsta sudjelovanja
Poster
Vrsta recenzije
Međunarodna recenzija
Ključne riječi
QUENCH experiment; cladding oxidation; hydrogen source term
Sažetak
The QUENCH program is a research program running at Karlsruhe Research Center (FZK – Forschungszentrum Karlsruhe) that is focused on the investigation of cladding behaviour and hydrogen source term following the water injection in the uncovered core of a light water reactor (LWR). Injection of water in the reactor pressure vessel (RPV) is one of the most important accident management measures to terminate a possible severe accident in a nuclear power plant (NPP). Boil-off experiment QUENCH-11 was performed at FZK on 8 December 2005 as the second of two experiments in the frame of the EC-supported LACOMERA program. The experiment was focused on studying bundle behaviour during boil-off and subsequent quenching at a small water injection rate. The test section (test bundle) consisted of 20 electrically heated fuel rod simulators surrounded by an insulating shroud. At the beginning of the experiment the test bundle had been filled with water up to the 2/3 of its length. A steady boil-off and a consequent top-down uncovery of the bundle were initiated by applying electrical power. After 1.5 hour of the experiment, approximately 10 kg of water in the period of 500 s was injected to cool down the bundle. Most of hydrogen was produced during that quenching phase. Analysis of the experiment was done with RELAP5/SCDAPSIM computer code which has the capability to model the cladding oxidation process – formation of ZrO2 layer on the outside cladding surface, the core heat-up due to oxidation and subsequent hydrogen production. The main results of the calculation are presented and compared with the experimental data.
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