Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity (CROSBI ID 551188)
Prilog sa skupa u zborniku | izvorni znanstveni rad | međunarodna recenzija
Podaci o odgovornosti
Šadek, Siniša ; Špalj, Srđan ; Glaser, Bruno
engleski
Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity
RELAP5/SCDAPSIM and MAAP4 are two widely used severe accident computer codes for the integral analysis of the core and the Reactor Pressure Vessel (RPV) behaviour following the core degradation. Additionally, MAAP4 code has the capability to simulate containment response after release of the primary system inventory. MAAP4 is a fast-running parametric code that produces credible results although it utilizes the simplified form of the conservation equations and the coarser discretization of the reactor systems. RELAP5/SCDAPSIM code is a best-estimate code that contains more mechanistic physics models than the other codes for both severe accident and thermal-hydraulic phenomena. The objective of the paper was to compare code results by applying different modelling options and to evaluate influence of thermal-hydraulic conditions on core damage progression. The intention was not general validation of codes but examination of code results for the same specific transient by using qualified input models. The analysed transient was postulated Station Blackout (SBO) in NPP Krško with a leakage from Reactor Coolant Pumps (RCP) seals. Two groups of runs were performed where each group had a different break area and thus a different leakage rate from the Reactor Coolant System (RCS). Break flow areas differed by a factor of two. The target results were the time when the molten core material slumps to the lower head and the time when the lower head wall fails due to interaction with the molten material. Parameters which affect core melt accident progression and debris bed behaviour in the lower head were discussed and their impact on RELAP5/SCDAPSIM and MAAP4 results were presented. Integrity of the RPV lower head was assessed using a) COUPLE code that is a two-dimensional, finite element heat conduction code incorporated in the RELAP5/SCDAPSIM code, and b) the relevant MAAP4 lower head models.
MAAP4; SCDAP/RELAP5; vessel integrity
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Podaci o prilogu
A1-107.1-A1-107.18.
2008.
objavljeno
Podaci o matičnoj publikaciji
Proceedings of the TopSafe 2008 Conference
D'Auria, Francesco ; Čavlina, Nikola
Brisel: European Nuclear Society (ENS)
978-92-95064-06-5
Podaci o skupu
TopSafe 2008 Conference
predavanje
30.09.2008-03.10.2008
Dubrovnik, Hrvatska