EASY – Evidence of design basis accidents mitigation solely with passive safety systems

Autor: Buchholz, S., Schaffrath, A., Bonfigli, G., Kaczmarkiewicz, N., Sporn, M., Schäfer, F., Wagner, T.
Jazyk: angličtina
Rok vydání: 2018
Předmět:
Zdroj: Jahrestagung Kerntechnik, Annual Meeting on Nuclear Technology, 29.-30.05.2018, Berlin, Deutschland
Jahrestagung Kerntechnik, Annual Meeting on Nuclear Technology, 29.-30.05.2018, Berlin, DeutschlandEASY – Evidence of design basis accidents mitigation solely with passive safety systems
Popis: Current advanced reactor designs of generation III and III+ as well as SMR are extensively providing passive safety systems in order to control design basis accidents. Assessment of these systems is needed to verify their functionality. This can be done by experiments and computer calculations. For the latter, well validated computer codes are needed, which are able to simulate the behaviour of these systems reliably. On the basis of the KERENA reactor concept (AREVA) the currently running EASY project is performed to validate and enhance the code system AC2 for such applications. Experimental data of the large scaled INKA test facility in Karlstein (Main) is used for the validation process. During EASY, model improvement of AC2 as well as validation calculations are performed. Beside the enhancement of the coupling between the two codes ATHLET and COCOSYS, a model for the simulation of the behaviour of the passive flooding valve has been created. Additionally the 3D model of ATHLET has been enhanced in order to simulate a water surface within the 3D domain of a large water pool (e.g. for the core flooding pool in KERENA). Validation of AC2 is performed in two steps: At first single component tests with fixed boundary conditions performed at INKA in the past are used. The second step is the validation of AC2 against in EASY performed new experiments regarding design basis accidents of KERENA (SB-LOCA, LB-LOCA and SBO).
Databáze: OpenAIRE
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