Adaptation of the ASTEC code system to accident scenarios in fusion installations

• Published in: Fusion engineering and design 2013-10, Vol.88 (9-10), p.2698-2703
• Main Authors: Séropian, C., Barrachin, M., Van Dorsselaere, J.P., Vola, D.
• Format: Article
• Language: English
• Subjects: Accidental impacts; Accidents; Adaptation; ASTEC; Design engineering; Fusion safety; In-vessel events; ITER; Nuclear engineering; Nuclear fusion; Pressurized water reactors; Walls
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2013.02.058

► IRSN has a first version of ASTEC able to model an accident in ITER. ► Models are developed to make possible water/air ingress simulations in the vessel. ► Some thermal-hydraulic calculations in agreement with MELCOR are discussed. ASTEC is a code system aiming to compute severe accident scenarios and their consequences in nuclear fission Pressurized Water Reactors (PWRs). Its capabilities have been recently extended to address the main accident sequences which may occur in the fusion installations, in particular in ITER. The purpose of this paper is to present a synthesis of the work that has been performed on ASTEC as part of its adaptation to fusion ITER facility, in particular concerning the development of some specific models (dust behavior, jet impaction and wall oxidation), the state of validation of the code and some first calculations for accident transients considered in the basis design. Comparisons with the MELCOR code, selected by ITER for their own safety analysis are provided and show a good agreement between both codes.