Ahmed Bentaïb

ORCID: 0000-0002-9540-5515
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About
Contact & Profiles
Research Areas
  • Combustion and Detonation Processes
  • Risk and Safety Analysis
  • Nuclear Materials and Properties
  • Nuclear and radioactivity studies
  • Nuclear reactor physics and engineering
  • Nuclear Engineering Thermal-Hydraulics
  • Combustion and flame dynamics
  • Fire dynamics and safety research
  • Graphite, nuclear technology, radiation studies
  • Radioactive contamination and transfer
  • Advanced Combustion Engine Technologies
  • Fusion materials and technologies
  • Gas Dynamics and Kinetic Theory
  • Particle Dynamics in Fluid Flows
  • Computational Fluid Dynamics and Aerodynamics
  • Energetic Materials and Combustion
  • French Urban and Social Studies
  • Oil and Gas Production Techniques
  • Sustainable Building Design and Assessment
  • Recycling and Waste Management Techniques
  • Cardiac Arrest and Resuscitation
  • Fluid Dynamics and Heat Transfer
  • Water Governance and Infrastructure
  • Cold Fusion and Nuclear Reactions
  • Advanced Power Generation Technologies

Institut de Radioprotection et de Sûreté Nucléaire
2015-2024

During the course of a severe accident in light water nuclear reactor, large amounts hydrogen can be generated and released into containment during reactor core degradation. Additional burnable gases [hydrogen (H2) carbon monoxide (CO)] may corium/concrete interaction. This could subsequently raise combustion hazard. As Fukushima accidents revealed, cause high pressure spikes that challenge buildings lead to failure surrounding buildings. To prevent gas explosion hazard, most mitigation...

10.1016/j.net.2014.12.001 article EN cc-by-nc-nd Nuclear Engineering and Technology 2015-02-01

10.1016/j.proci.2018.06.082 article EN publisher-specific-oa Proceedings of the Combustion Institute 2018-07-31

AbstractAbstractWithin the course of a hypothetical severe accident in nuclear power plant, hydrogen can be generated primary circuit and released into containment. Considering possibility deflagration, simulation distribution containment by computer codes is major importance. To create database for code validation, several experiments using helium have been performed German Thermal Hydraulics, Hydrogen, Aerosols, Iodine (THAI) facility. The started with TH13 test, which was base...

10.13182/nt11-a12508 article EN Nuclear Technology 2011-09-01

Severe Accidents (SA) developments are closely and deeply linked with thermal-hydraulics, that is, fluid flow combined heat mass transfer. The present paper synthesizes this relation during an accident unfolding provides overview of the remaining gaps associated to thermal-hydraulics need be addressed reduce uncertainties SA optimize their management. Some those thermal–hydraulic phenomena common other areas, but most them genuine domain. In addition affecting development, there others major...

10.1016/j.nucengdes.2023.112256 article EN cc-by-nc-nd Nuclear Engineering and Design 2023-03-24

The French Institut de Radioprotection et Sûreté Nucléaire (IRSN) and the German Gesellschaft für Anlagen und Reaktorsicherheit mbH (GRS) have been jointly developing for several years a system of calculation codes (or "integral" code), ASTEC (Accident Source Term Evaluation Code), to simulate complete scenario hypothetical severe accident in nuclear light water reactor from initiating event through possible radiological release fission products out containment, so-called "source term." Very...

10.13182/nt10-a10326 article EN Nuclear Technology 2010-06-01

The aim of the present work is to identify and characterize type combustion hydrogen-air mixtures near flammability limits for different initial temperatures (from 298 423 K) pressures (100 250 kPa) relevant pressurized water reactor conditions. This experimental study has been carried out using a spherical vessel equipped with pressure transducer monitor increase subsequent two optical windows record flame propagation. From schlieren images, regimes propagation have identified depending on...

10.13182/nt12-a13543 article EN Nuclear Technology 2012-04-01

This paper presents a methodology and its application to Level 2 Probabilistic Safety Assessment (PSA-2), evaluate the impact of Passive Autocatalytic Recombiners (PARs) on hydrogen risk in reactor containment case severe accident. Among whole set accidental scenarios calculated framework PSA-2, nine have been selected as representative terms in-vessel production rate total produced mass. Five complementary added core reflooding situations. For this evolution conditions (i.e., pressure,...

10.1155/2010/320396 article EN cc-by Science and Technology of Nuclear Installations 2010-01-01

In the case of a severe accident inside water-cooled fusion facility, like ITER, there exist several scenarios in which hydrogen may be produced and released into suppression tank. Assuming accidental ingress air, formation flammable gas mixtures lead to explosions component failure. One option mitigate such hypothetical is installation passive auto-catalytic recombiners (PARs), are presently used as safety devices containments nuclear fission reactors. PARs convert water vapor by means...

10.1016/j.fusengdes.2017.02.019 article EN cc-by Fusion Engineering and Design 2017-02-08
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