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A new major version of the European severe accident integral code ASTEC, developed by IRSN with some GRS support, was delivered in November 2015 to the ASTEC worldwide community.Main modelling features of this V2.1 version are summarised in this paper. In particular, the in-vessel coupling technique between the reactor coolant system thermal-hydrau...
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... Besides an extension of the existing experimental database on existing and innovative filtration systems, the focus was put on trying to get a deeper understanding of the phenomena underlying their performance and to develop models/correlations that allow modelling of the systems in severe accident analysis codes, like ASTEC (Chatelard et al., 2015). ...
... Globally, in-depth analysis of the experimental results allowed a deeper understanding of the phenomena involved in the performance of the mitigation systems studied, and simple models or correlations which should be easy to implement in accident analysis codes, like ASTEC (Chatelard et al., 2015) could be proposed for several PASSAM experimental studies. ...
The PASSAM (Passive and Active Systems on Severe Accident source term Mitigation) project was launched in the frame of the 7th framework programme of the European Commission. Coordinated by
IRSN, this four year project (2013–2016) involved nine partners from six countries: IRSN, EDF and university of Lorraine (France); CIEMAT and CSIC (Spain); PSI (Switzerland); RSE (Italy); VTT (Finland) and
AREVA GmbH (Germany).
It was mainly an R&D project of experimental nature aimed at investigating phenomena that might enhance source term mitigation in case of a severe accident in a Nuclear Power Plant (NPP). Both existing systems (i.e., water scrubbing and sand bed filters plus metallic pre-filters) and innovative ones (i.e., high pressure sprays, electrostatic precipitators, acoustic agglomerators and, advanced zeolites and combined wet-dry filtration systems), were experimentally studied in conditions as close as possible from those anticipated for severe accidents.
This paper presents the main experimental results of the project which represent a significant extension of the current database on these existing or innovative mitigation systems. Application of some of
these data for improving existing models or developing new ones should eventually enhance the capability of modelling Severe Accident Management measures and developing improved guidelines
... under the 7 th Framework programme [2], which included source term studies [3]. Phébus FP and associated studies [4] provide outstanding insights into fission product release and transport and, particularly, containment iodine chemistry, which are encapsulated in recent versions of integral severe accident analysis codes like ASTEC 2.1 [5], MELCOR 2.1 [6] and MAAP-EDF [7], while data from international projects such as the International Source Term Project (ISTP) [8], EC/PASSAM [9] and Organisation for Economic Cooperation and Development (OECD)/BIP&BIP2, THAI&THAI2, and STEM [1] are being interpreted with a view to further code improvements. Nevertheless, some issues still remain and need addressing [10]. ...
... and EURATOM, e.g. the SARNET Network of Excellence under the 7 th Framework programme [2], which included source term studies [3]. Phébus FP and associated studies [4] provide outstanding insights into fission product release and transport and, particularly, containment iodine chemistry, which are encapsulated in recent versions of integral severe accident analysis codes like ASTEC 2.1 [5], MELCOR 2.1 [6] and MAAP-EDF [7], while data from international projects such as ISTP [8], EC/PASSAM [9] and OECD/BIP&BIP2, THAI&THAI2, and STEM [1] are being interpreted with a view to further code improvements. Nevertheless, some issues still remain and need addressing [10]. ...
The integrated ICE (Ingress-of-Coolant Event) facility, scaled 1/1600 with respect to the ITER-FEAT design, was built at JAERI with the aim of reproducing the phenomenology occurring in an ICE accident. An ICE occurs when a rupture in the coolant pipes causes the pressurized coolant to enter into the Plasma Chamber, which is held under high vacuum condition. A suppression system is used to mitigate the overpressurization and to prevent mechanical damages to the structures. The CPA module of the ASTEC severe accident code (Study carried out with ASTEC V2, IRSN all rights reserved, [2020]), has been adopted for the modelling and the simulation of a test conducted in the ICE facility. The experimental results of the main thermal-hydraulic parameters have been compared to the code results to characterize the ASTEC capability to predict the phenomenology of a low-pressure two-phase flow transient occurring in a fusion reactor. By coupling the ASTEC code with the uncertainty tool RAVEN, developed by Idaho National Laboratory, an uncertainty analysis has been conducted on the transient. The aim of the present activity is to investigate the dispersion and the sensitivity of the code response to the variation of selected uncertain input parameters, which could influence the simulation of an ICE. The activity also provides a first application of uncertainty analysis through the RAVEN-ASTEC coupling.