The present work has been carried out in the context of the development and validation of a set of “reference” ASTEC input decks for the main generic types of nuclear power plants (NPPs) in Europe; in the CESAM (Code for European Severe Accident Management) project, where JRC is contributing in several of the six working packages (WPs) in which it is divided. The JRC team have used the PWR900 model (delivered by IRSN to CESAM partners in February 2014) to simulate two accidents, a LBLOCA (Large-Break, Loss-Of-Coolant Accident) and a LFW (Loss of Feed Water), in order to confirm the ASTEC v2.0r3 capabilities. The assessment was done comparing the evolutions of these accidents vs. MAAP 4.0.8 code. To perform such kind of comparison, JRC developed a specific MAAP4 input deck for a pressurized water reactor (PWR) of 900 MWe. This input deck is based on a generic MAAP4 input deck, which has been adapted to correspond to the best extent possible to the ASTEC V2.0r3 PWR900 model. The comparisons focus only on in-vessel thermal hydraulics phenomena, core degradation and corium behaviour in the lower head. The calculations stop as soon as the reactor pressure vessel fails. The comparisons of the main thermo-hydraulic variables between the two code results are detailed in this paper and are satisfactory overall.

VELA GARCIA Monica;  SANGIORGI Marco;  HERMSMEYER Stephan; 

2015-09-30

VOYAGES C.MATHEZ

JRC95042

www.matheztravel.com/demo/downloads/pour_proceedings.rar,    https://publications.jrc.ec.europa.eu/repository/handle/JRC95042,