Jean-Pierre Van Dorsselaere
Institut de radioprotection et de sûreté nucléaire
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Science and Technology of Nuclear Installations | 2012
Jean-Pierre Van Dorsselaere; Ari Auvinen; D. Beraha; P. Chatelard; Christophe Journeau; I. Kljenak; Alexei Miassoedov; Sandro Paci; T. h. W. Tromm; R. Zeyen
Forty-three organisations from 22 countries network their capacities of research in SARNET (Severe Accident Research NETwork of excellence) to resolve the most important remaining uncertainties and safety issues on severe accidents in existing and future water-cooled nuclear power plants (NPP). After a first project in the 6th Framework Programme (FP6) of the European Commission, the SARNET2 project, coordinated by IRSN, started in April 2009 for 4 years in the FP7 frame. After 2,5 years, some main outcomes of joint research (modelling and experiments) by the network members on the highest priority issues are presented: in-vessel degraded core coolability, molten-corium-concrete-interaction, containment phenomena (water spray, hydrogen combustion…), source term issues (mainly iodine behaviour). The ASTEC integral computer code, jointly developed by IRSN and GRS to predict the NPP SA behaviour, capitalizes in terms of models the knowledge produced in the network: a few validation results are presented. For dissemination of knowledge, an educational 1-week course was organized for young researchers or students in January 2011, and a two-day course is planned mid-2012 for senior staff. Mobility of young researchers or students between the European partners is being promoted. The ERMSAR conference is becoming the major worldwide conference on SA research.
Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum | 2006
Cataldo Caroli; Alexandre Bleyer; A. Bentaib; P. Chatelard; M. Cranga; Jean-Pierre Van Dorsselaere
IRSN uses a two-tier approach for development of codes analysing the course of a hypothetical severe accident (SA) in a Pressurized Water Reactor (PWR): on one hand, the integral code ASTEC, jointly developed by IRSN and GRS, for fast-running and complete analysis of a sequence; on the other hand, detailed codes for best-estimate analysis of some phenomena such as ICARE/CATHARE, MC3D (for steam explosion), CROCO and TONUS. They have been extensively used to support the level 2 Probabilistic Safety Assessment of the 900 MWe PWR and, in general, for the safety analysis of the French PWR. In particular the codes ICARE/CATHARE, CROCO, MEDICIS (module of ASTEC) and TONUS are used to support the safety assessment of the European Pressurized Reactor (EPR). The ICARE/CATHARE code system has been developed for the detailed evaluation of SA consequences in a PWR primary system. It is composed of the coupling of the core degradation IRSN code ICARE2 and of the thermalhydraulics French code CATHARE2. The CFD code CROCO describes the corium flow in the spreading compartment. Heat transfer to the surrounding atmosphere and to the basemat, leading to the possible formation of an upper and lower crust, basemat ablation and gas sparging through the flow are modelled. CROCO has been validated against a wide experimental basis, including the CORINE, KATS and VULCANO programs. MEDICIS simulates MCCI (Molten-Corium-Concrete-Interaction) using a lumped-parameter approach. Its models are being continuously improved through the interpretation of most MCCI experiments (OECD-CCI, ACE[[ellipsis]]). The TONUS code has been developed by IRSN in collaboration with CEA for the analysis of the hydrogen risk (both distribution and combustion) in the reactor containment. The analyses carried out to support the EPR safety assessment are based on a CFD formulation. At this purpose a low-Mach number multi-component Navier-Stokes solver is used to analyse the hydrogen distribution. Presence of air, steam and hydrogen is considered as well as turbulence, condensation and heat transfer in the containment walls. Passive autocatalytic recombiners are also modelled. Hydrogen combustion is afterwards analysed solving the compressible Euler equations coupled with combustion models. Examples of on-going applications of these codes to the EPR safety analysis are presented to illustrate their potentialities.Copyright
Science and Technology of Nuclear Installations | 2012
Sandro Paci; Jean-Pierre Van Dorsselaere
The SARNET2 (severe accidents Research NETwork of Excellence) project started in April 2009 for 4 years in the 7th Framework Programme (FP7) of the European Commission (EC), following a similar first project in FP6. Forty-seven organisations from 24 countries network their capacities of research in the severe accident (SA) field inside SARNET to resolve the most important remaining uncertainties and safety issues on SA in water-cooled nuclear power plants (NPPs). The network includes a large majority of the European actors involved in SA research plus a few non-European relevant ones. nThe “Education and Training” programme in SARNET is a series of actions foreseen in this network for the “spreading of excellence.” It is focused on raising the competence level of Master and Ph.D. students and young researchers engaged in SA research and on organizing information/training courses for NPP staff or regulatory authorities (but also for researchers) interested in SA management procedures.
Archive | 2011
Jean-Pierre Van Dorsselaere; T. Albiol; Jean-Claude Micaelli
Severe accidents (SA) in nuclear power plants (NPPs) are unlikely events but with serious consequences, as recently shown by the accident that occurred in April 2011 in the Fukushima Japanese NPPs. SA research started originally in the seventies with initial risk assessment studies and later on with experimental programs, development of numerical simulation codes, and Level 2 Probabilistic Safety Assessments (PSA2). A huge amount of research and development (RD then in the Chernobyl RBMK (Watercooled channel-type reactors with graphite as moderator, designed by Soviet Union) reactor in Ukraine. Large progress has been reached in recent years on the understanding of SA but several issues still need research activities to reduce uncertainties and consolidate the accident management plans. Along with the progress of understanding and the limited amount of the national budgets on SA RD Micaelli et al., 2005), in the framework of the 6th Framework Programme (FP6) of the European Commission, gathering most worldwide actors on R&D SA. One of the main outcomes was the identification of the highest priority SA issues still to be solved. A second phase of the network (SARNET2 project) has started in April 2009, again supported by EC in the FP7 for four years, again coordinated by IRSN. Section 2 describes shortly what a severe accident is (most of the material described in this section is issued from the reference IRSN-CEA, 2007). Section 3 presents the general approach on SA R&D. Section 4 explains in details the approach that was adopted in SARNET to rank the R&D priorities. Section 5 describes the current SARNET2 FP7 project and the common research programmes, and finally Section 6 focuses, for the sake of illustration, on the important issue of coolability of a degraded core during reflooding.
Congrès international European Nuclear Conference (ENC2005) | 2006
Jean-Claude Micaelli; T. Haste; Jean-Pierre Van Dorsselaere; Jean-Michel Bonnet; Leonhard Meyer; D. Beraha; Alessandro Annunziato; B. Chaumont; Bernard Adroguer; Raj Sehgal; Klaus Trambauer
Nuclear Engineering and Design | 2011
Jean-Pierre Van Dorsselaere; T. Albiol; B. Chaumont; T. Haste; Christophe Journeau; Leonhard Meyer; Bal Raj Sehgal; B. Schwinges; D. Beraha; Alessandro Annunziato; R. Zeyen
Nuclear Engineering and Design | 2006
Jean-Pierre Van Dorsselaere; Florian Fichot; Jean-Marie Seiler
Annals of Nuclear Energy | 2014
Jean-Pierre Van Dorsselaere; Sandro Paci
NUGENIA 2018 General Forum | 2018
Jean-Pierre Van Dorsselaere; Brechignac François; L.E. Herranz; Piluso Pascal; Kljenak Ivo; Miassoedov Alexei; Sandro Paci
EPJ Nuclear Sciences & Technologies | 2017
Jean-Pierre Van Dorsselaere; François Bréchignac; Felice De Rosa; L.E. Herranz; Ivo Kljenak; Alexei Miassoedov; Sandro Paci; Pascal Piluso