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Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum | 2006

The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR

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

Containment Thermal-Hydraulic Simulations With an LP-CFD Approach: Qualification Matrix of the TONUS Code

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

The TONUS CFD code for hydrogen risk analysis : Physical models, numerical schemes and validation matrix

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

OVERVIEW ON HYDROGEN RISK RESEARCH AND DEVELOPMENT ACTIVITIES: METHODOLOGY AND OPEN ISSUES

A. Bentaib; Nicolas Meynet; Alexandre Bleyer


Nuclear Engineering and Design | 2014

Overview of the independent ASTEC V2.0 validation by SARNET partners

P. Chatelard; Siegfried Arndt; Boryana Atanasova; Giacomino Bandini; Alexandre Bleyer; Thimo Brähler; Michael Buck; Ivo Kljenak; Bohumir Kujal


Nuclear Engineering and Design | 2016

Outcomes from the EURATOM-ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management

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

EUROATOM-ROSATOM-ERCOSAM-SAMARA Projects - Scaling from Nuclear Power plant to experiments

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

Evaluation of the pressure loads generated by hydrogen explosion in auxiliary nuclear building

A. Bentaib; Alexandre Bleyer; Pierre Pailhories; Jean-Pierre L'heriteau; Bernard Chaumont; Jerome Dupas; Jerome Riviere


8th Conference on Severe Accident Research (ERMSAR) | 2017

Benchmark exercise TH27 on natural convection with steam injection and condensation inside the extended THAI facility

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

Characterisation of metal combustion with DUST code

J.R. García-Cascales; F.J.S. Velasco; Ramón A. Otón-Martínez; S. Espín-Tolosa; A. Bentaib; Nicolas Meynet; Alexandre Bleyer

Collaboration


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A. Bentaib

Institut de radioprotection et de sûreté nucléaire

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J. Malet

Institut de radioprotection et de sûreté nucléaire

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Cataldo Caroli

Institut de radioprotection et de sûreté nucléaire

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Lasse Götz

RWTH Aachen University

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Stefan Benz

Karlsruhe Institute of Technology

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Stephan Kelm

Forschungszentrum Jülich

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Thomas Jordan

Karlsruhe Institute of Technology

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Emmanuel Porcheron

Institut de radioprotection et de sûreté nucléaire

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