Please use this identifier to cite or link to this item:
|Title:||CESAM – Code for European Severe Accident Management|
|Authors:||NOWACK H.; CHAILAN L.; CHATELARD P.; HERMSMEYER STEPHAN; SANCHEZ V.; HERRANZ LUIS|
|Type:||Articles in periodicals and books|
|Abstract:||The CESAM FP7 project of EURATOM has been conducted from April 2013 until March 2017 in the aftermath of the Fukushima Dai-ichi accidents. Nineteen international partners from Europe and India, including the European Joint Research Centre, have been participating under the coordination of GRS and with a strong involvement of IRSN that were both the code developers. The Project objectives were in priority an improved understanding of all relevant phenomena during the Fukushima Dai-ichi accidents and their importance for Severe Accident Management (SAM) measures as well as the improvement of the ASTEC computer code to simulate plant behaviour throughout accident sequences including SAM measures. One starting step was the analysis of current SAM measures implemented in European plants. In order to achieve these goals, simulations of relevant experiments that allow a solid validation of the ASTEC code against single and separate effect tests have been conducted. Covered topics in the CESAM project have been grouped in 9 different areas among which are re-flooding of degraded cores, pool scrubbing, hydrogen combustion, or spent fuel pools behaviour. Furthermore, modelling improvements have been implemented in the current ASTEC V2.1 series for the estimation of source term consequences in the environment and the prediction of plant status in emergency centres. Finally, ASTEC reference input decks have been created for all reactor types operated in Europe today as well as for spent fuel pools. These reference input decks generically describe plant types like PWR, BWR, and VVER without defining proprietary data of a special plant and they account for the best recommendations from code developers. In addition, also a generic input deck for a spent fuel pool was elaborated. These input decks can be used as basis by all (and especially new) ASTEC users in order to implement the specificities of their specific plant. Within CESAM, benchmark calculations have been performed with other codes (such as MELCOR, MAAP, ATHLET-CD, COCOSYS…) with a focus on the effectiveness of currently implemented SAM measures based on these generic inputs. This article will provide first a final summary of the CESAM project. Therefore, an overview of the improved modelling capabilities of the recent ASTEC V2.1 version is given followed by the validation status of ASTEC V2.1 as concluded after CESAM. Further, plant applications performed by CESAM partners will be summarized with a special focus on simulation of SAM measures in various NPP types and finally, insights gained on SAM measures will be derived.|
|JRC Directorate:||Nuclear Safety and Security|
Files in This Item:
There are no files associated with this item.
Items in repository are protected by copyright, with all rights reserved, unless otherwise indicated.