Alexandre Bleyer
Institut de radioprotection et de sûreté nucléaire
Network
Latest external collaboration on country level. Dive into details by clicking on the dots.
Publication
Featured researches published by Alexandre Bleyer.
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
14th International Conference on Nuclear Engineering | 2006
A. Bentaib; Alexandre Bleyer; J. Malet; Cataldo Caroli; J. Vendel; S. Kudriakov; F. Dabbene; E. Studer; A. Beccantini; J. P. Magnaud; H. Paillère
The French Atomic Energy Commission (CEA) and the Institute for Radiological Protection and Nuclear Safety (IRSN) are developing a hydrogen risk analysis code (safety code) which incorporates both lumped parameter (LP) and computational fluid dynamics (CFD) formulations. In this paper we present briefly the main physical models for containment thermal-hydraulics. Validation and typical numerical results will be presented for hydrogen distribution and combustion applications in small and realistic large geometries.Copyright
Nuclear Engineering and Design | 2008
S. Kudriakov; F. Dabbene; E. Studer; A. Beccantini; J.P. Magnaud; H. Paillère; A. Bentaib; Alexandre Bleyer; J. Malet; Emmanuel Porcheron; Cataldo Caroli
Nuclear Engineering and Technology | 2015
A. Bentaib; Nicolas Meynet; Alexandre Bleyer
Nuclear Engineering and Design | 2014
P. Chatelard; Siegfried Arndt; Boryana Atanasova; Giacomino Bandini; Alexandre Bleyer; Thimo Brähler; Michael Buck; Ivo Kljenak; Bohumir Kujal
Nuclear Engineering and Design | 2016
Domenico Paladino; Michele Andreani; Salih Guentay; Guillaume Mignot; Ralf Kapulla; Sidharth Paranjape; Medhat Sharabi; Arkadi Kisselev; Tatiana Yudina; Aleksandr Filippov; Mikhail Kamnev; Akhmir Khizbullin; Oleg Tyurikov; Zhe (Rita) Liang; Danièle Abdo; Jérôme Brinster; Frédéric Dabbene; Stephan Kelm; Michael Klauck; Lasse Götz; Rebekka Gehr; J. Malet; A. Bentaib; Alexandre Bleyer; Pascal Lemaitre; Emmanuel Porcheron; Stefan Benz; Thomas Jordan; Zhanjie Xu; Christopher Boyd
International Congress on Advances in Nuclear Power Plants (ICAPP 2015) | 2015
S. Benteboula; Stefan Benz; A. Loukianov; I. Tkatschenko; Michele Andreani; J. Malet; Alexandre Bleyer; M. Kamnev; A. Filippov; S. Guentay; Stephan Kelm; D.C. Visser; Z. Liang; Thomas Jordan; A. Khizbullin; Hans-Josef Allelein; T. Yudina; Domenico Paladino; A. Zaytsev; A. Bentaib; J. Brister; A. Kiselev
Archive | 2005
A. Bentaib; Alexandre Bleyer; Pierre Pailhories; Jean-Pierre L'heriteau; Bernard Chaumont; Jerome Dupas; Jerome Riviere
8th Conference on Severe Accident Research (ERMSAR) | 2017
M. Freitag; T. Risken; P. Royl; Lasse Götz; A. Mansour; I. Kljenak; M. Povilaitis; S. Schwarz; A. Bentaib; Michael Klauck; P. Kostka; A. Siccama; T. Jankowski; T. Janda; Alexandre Bleyer
Fusion Engineering and Design | 2015
J.R. García-Cascales; F.J.S. Velasco; Ramón A. Otón-Martínez; S. Espín-Tolosa; A. Bentaib; Nicolas Meynet; Alexandre Bleyer