Jules Delacroix

ORCID: 0000-0003-0276-4146
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About
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Research Areas
  • Nuclear Materials and Properties
  • Nuclear reactor physics and engineering
  • Metallurgical Processes and Thermodynamics
  • Fluid Dynamics and Thin Films
  • Characterization and Applications of Magnetic Nanoparticles
  • Fusion materials and technologies
  • Nuclear and radioactivity studies
  • Solidification and crystal growth phenomena
  • Graphite, nuclear technology, radiation studies
  • Rheology and Fluid Dynamics Studies
  • Radioactive contamination and transfer
  • Fluid Dynamics and Heat Transfer
  • Nuclear Physics and Applications
  • Radioactive element chemistry and processing
  • Fluid Dynamics and Turbulent Flows
  • Nuclear Engineering Thermal-Hydraulics
  • Electron and X-Ray Spectroscopy Techniques
  • nanoparticles nucleation surface interactions
  • Theoretical and Computational Physics
  • Fluid Dynamics and Mixing
  • Microfluidic and Bio-sensing Technologies
  • Fluid Dynamics and Vibration Analysis
  • Thermography and Photoacoustic Techniques
  • Thermodynamic and Structural Properties of Metals and Alloys
  • Electromagnetic Compatibility and Noise Suppression

CEA Cadarache
2017-2024

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2017-2024

Direction des énergies
2018-2021

Science et Ingénierie des Matériaux et Procédés
2014-2019

Université Grenoble Alpes
2014-2018

Centre National de la Recherche Scientifique
2015-2018

Institut polytechnique de Grenoble
2015-2018

CEA Grenoble
2018

Within the framework of welding steel components in pressurized water reactors, optimization weld pool penetration is a major issue. The thermal‐hydraulics molten can be driven by Marangoni flows at free surface. To compute these flows, liquid steel's thermophysical properties such as density ρ and surface tension σ are required. Such for austenitic vessel AISI 304L state scarce, even not available above 1800 °C, due to technological issues. viscometer temperature installation (VITI)...

10.1002/srin.202100624 article EN steel research international 2022-01-04

In the current context of nuclear revival under constraint global warming and an ever-increasing world demand for energy, it is essential to take all precautions in event a serious accident during design phase review severe mitigation features existing plants. The accompanied by development prototypes based on alternative concepts light water reactors, such as Sodium-cooled Fast Reactor (SFR), High Temperature (HTR), Molten Salt (MSR), which are also consideration reactors reduced power...

10.1016/j.nucengdes.2024.113055 article EN cc-by-nc-nd Nuclear Engineering and Design 2024-03-12

Thermophysical properties of liquid metal alloys play a crucial role in the variety processes. Present work reports experimental investigations two new transformation induced plasticity (TRIP) steels. A classical maximum bubble pressure technique is successfully used to measure surface tension and density TRIP‐steel samples temperatures range 1500–1800 °C. Experiments are performed different measurement cells from TU Freiberg Commissariat l'Energie Atomique (CEA), Cadarache. Capillaries made...

10.1002/srin.202000260 article EN cc-by steel research international 2020-08-04

As a first step towards two-phase magnetohydrodynamics (MHD), this paper addresses an original analytical coupling between surface rheology, e.g., gradually oxidizing liquid metal surface, ruled by the Boussinesq number Bo, and supporting annular MHD flow, Hartmann Ha, in general layout of classical deep-channel viscometer, as developed Mannheimer Schechter [J. Colloid Interface Sci. 32, 195–211 (1970)]. Using matched asymptotic expansion based on small parameter 1/Ha, we can express...

10.1063/1.4869327 article EN Physics of Fluids 2014-03-01

During a severe accident in nuclear reactor, the molten core—or corium—may be relocated into reactor vessel’s lower plenum case of core support plate failure. The management strategy for In-Vessel Retention—or IVR—consists stabilizing corium within pressure vessel by external cooling head. If now, fails due to excessive thermal loading on its walls, Ex-Vessel EVR—strategy is adopted. In this case, melt stabilization can achieved effective spreading, either cavity or dedicated “core-catcher”,...

10.3389/fenrg.2022.883972 article EN cc-by Frontiers in Energy Research 2022-05-26

In-vessel retention (IVR) is an attractive strategy to mitigate a severe accident. However, because of low margins, it remains questionable for reactors power 1000 MW(electric) and higher. The success the IVR mainly depends on mechanical behavior vessel after being ablated inner thermal load, i.e., heat flux transferred by molten pool vessel, which has remain lower than critical flux. In some configurations, stratification may lead concentration in conductive metallic layer. An understanding...

10.1080/00295450.2018.1486160 article EN Nuclear Technology 2018-07-23

Within the ALISA (Access to Large Infrastructures for Severe Accidents) cooperation between European Union and China on SA (Severe Accident) facilities, CNPRI (China Nuclear Power technology Research Institute) has proposed CEA (Commissariat à l'Energie Atomique et aux Energies Alternatives) a series of experiments determine density surface tension different oxidic mixtures representative from both in-vessel ex-vessel retention scenarios. This article describes those tests performed in VITI...

10.1299/mej.19-00611 article EN cc-by-nc-nd Mechanical Engineering Journal 2020-01-01

10.1016/j.nucengdes.2021.111266 article EN publisher-specific-oa Nuclear Engineering and Design 2021-05-23

The original coupling between the surface rheology of a liquid metal and supporting annular Couette magnetohydrodynamic (MHD) flow is theoretically numerically investigated in this paper, general layout classical viscometer, as developed by Mannheimer Schechter [“An improved apparatus analysis for rheological measurements,” J. Colloid Interface Sci. 32, 195–211 (1970)]. purely hydrodynamic interplay main azimuthal (induced rotating floor) secondary overturning (generated centrifugation)...

10.1063/1.4922711 article EN Physics of Fluids 2015-06-01

Channel viscosimetry makes it possible to estimate surface viscosity of a layer surfactants or metal oxides. A new model is presented with curvature effects accounted for, regardless whether not the supporting liquid wetting if contaminated Newtonian.

10.1103/physrevfluids.4.054002 article EN Physical Review Fluids 2019-05-13

This paper introduces an experimental apparatus which generates the end-driven annular flow of a liquid metal pervaded by uniform magnetic field. Unlike past viscometers involving channel with particular values depth-to-width ratio, present experiment enables us to drive viscous shear at surface bath put in rotation. The interaction parameter N and Boussinesq number related viscosity can be monitored from magnitude applied field; latter being set large enough for avoiding artefacts...

10.1063/1.5003256 article EN Review of Scientific Instruments 2018-01-01

Cs-bearing microparticles, released during the accident of Fukushima Daiichi, are a significant concern for health and environment due to their abundance over wide areas, associated with low solubility. Since discovery, efforts have been made characterise these particles use them as direct witnesses various events inside reactors. This study reports experimental synthesis micrometric through molten core-concrete interaction. Primary chemical analyses on Al/Si, K/Si Na/Si atomic ratios seem...

10.1016/j.nme.2022.101253 article EN cc-by-nc-nd Nuclear Materials and Energy 2022-09-16

As a first step towards the description of magnetohydrodynamic (MHD) dispersed two-phase flows, permanent MHD channel flow past stationary sphere is numerically investigated, highlighting gradual emergence atypical patterns, among them genuine ``ghost column.''

10.1103/physrevfluids.3.123701 article EN Physical Review Fluids 2018-12-05

Since the Fukushima-Daiichi accident, severe accident research has been reconsidered from another perspective. In case of a in nuclear reactor, core can melt to form corium, complex mixture molten fuel and structural materials. order improve reactor safety mitigate on site, it is important understand behaviour corium configurations. context in-vessel retention (IVR) studies, scientific community limited knowledge immiscible phase stratification phenomenon. This could be further developed...

10.1121/2.0001075 article EN Proceedings of meetings on acoustics 2019-01-01

10.1016/j.nucengdes.2018.06.027 article EN Nuclear Engineering and Design 2018-07-06

In the context of in-vessel retention (IVR) strategy in order to better assess risk reactor vessel failure, knowledge related kinetics immiscible liquid phases stratification phenomenon needs be further improved. So far, only one medium-scale experiment (MASCA-RCW, frame OECD MASCA program) gives direct information regarding transient relocation metal below oxide phase through post-mortem measurements. No experimental characterization inversion when heavy becomes lighter and relocates at top...

10.1051/epjconf/202022508003 article EN cc-by EPJ Web of Conferences 2020-01-01
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