Validation and Application of the AC2 Code COCOSYS

Author:

Reinke N.1,Arndt S.1,Bakalov I.1,Band S.1,Beck S.1,Nowack H.1,Iliev D.1,Spengler C.1,Klein-Hessling W.1,Sonnenkalb M.1

Affiliation:

1. 1Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Safety Research Division, Schwertnergasse 1, 60677 Köln

Abstract

AbstractThe GRS program package AC2 with its codes ATHLET/ATHLET-CD and COCOSYS aims for the reliable computational simulation of significant phenomena occurring during normal operation, design basis accidents, and severe accidents in the cooling circuit and containment of a nuclear power plant. To keep the modelling at the state-of-the-art, continuous development and validation is required. This is accomplished through participation in several national and international experimental research programs, where AC2 or one of its codes are assessed against both separate effect tests and integral tests. This paper exemplifies the status of validation and application of COCOSYS by means of calculations of iodine chemistry and molten corium/concrete interaction after reactor pressure vessel rupture. Further, calculations using the external 3D module CoPool coupled to COCOSYS on thermal stratification in large water pools are discussed. The examples given demonstrate the progress of the COCOSYS development and the capability to simulate phenomena in the containment during incidents and accidents with good results. Future applications comprise the entire spectrum of incidents and accidents for Generation III/III+ systems with just one program package.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

Reference16 articles.

1. Development of AC2 for the simulation of advanced reactor design of Generation 3/3+ and light water cooled SMRs

2. Iliev, O.; Iliev, D.; Steiner, K.; Zemitis, A.; Klein-Hessling, W.; Sonnenkalb, M.; Freitag, M.: Towards a combined CFD/LP code approach for containment simulations, Application of CFD/CMFD Codes to Nuclear Reactor Safety and Design and their Experimental Validation. Workshop Proceedings OECD/NEA-IAEA Workshop CFD4NRS-5, Zurich, 9–11 September, Zurich, 2014

3. The main outcomes of the OECD Behaviour of Iodine (BIP) Project

4. Necessary improvements of the GRS simulation chain for the simulation of light-water-cooled SMRs

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