Search Results - "Barrachin, M."
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Morphology and phase distributions of molten core in a reactor vessel
Published in Journal of nuclear materials (15-12-2020)“…•Experiments and thermodynamic analyses on morphology and phase equilibrium of corium.•NUCLEA analysis results on U-Zr-O-Fe system agreed well with the…”
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Diffusivity of hydrogen and properties of point defects in beryllium investigated by DFT
Published in Journal of nuclear materials (01-10-2019)“…Beryllium will be one of the plasma-facing materials for ITER. It will have to sustain high fluxes of hydrogen isotopes and as a consequence significant…”
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3
Hafnium oxidation at high temperature in steam
Published in Journal of nuclear materials (01-07-2021)“…To assess the potential impact of using hafnium as absorber material in LWRs in high temperature accidental situations, the oxidation behavior of hafnium was…”
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A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments
Published in Nuclear engineering and design (01-03-2015)“…•The results of the experiments CORA, QUENCH and Phébus SFD/FP are summarised.•All phenomena expected up to melt movement to the lower head are shown…”
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5
Contribution to a better evaluation of the dust speciation in case of an accident in ITER
Published in Fusion engineering and design (01-11-2017)“…•Thermodynamic properties of beryllium hydride.•Astec simulation of a wet-bypass scenario in the ITER facility.•Highlight the potential formation of beryllium…”
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6
Experimental study and thermodynamic modelling of the Ag-Cd-In system
Published in Calphad (01-03-2019)“…In the case of a severe accident, the silver-indium-cadmium alloy which constitutes the absorber rods of a pressurized water reactor is liable to melt,…”
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Progress on source term evaluation of accidental events in the experimental fusion installation ITER
Published in Fusion engineering and design (01-10-2015)“…•Progress of the IRSN R&D activities related to the safety assessment of the ITER installation.•Simulation of an accidental scenario with the ASTEC code: loss…”
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8
Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminum
Published in The Journal of chemical thermodynamics (01-01-2019)“…•The Zr dissolution in liquid Al in past calorimetry experiments are re-interpreted.•They must be considered in terms of transformation of Zr into Al3Zr.•It…”
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Enthalpy of mixing in the Ag-Cd-In ternary liquid phase
Published in The Journal of chemical thermodynamics (01-04-2017)“…•Mixing enthalpy in the Ag-Cd-In ternary liquid phase is measured for the first time.•Both Ag and Cd drop solution calorimetric experiments give consistent…”
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Theoretical prediction of thermodynamic properties of tritiated beryllium molecules and application to ITER source term
Published in Fusion engineering and design (01-10-2014)“…•Standard enthalpies of formation of BeH, BeH2, BeOH, Be(OH)2 have been calculated.•The impact of hydrogen isotopy on thermodynamic properties has been…”
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Fuel and fission product behaviour in early phases of a severe accident. Part II: Interpretation of the experimental results of the PHEBUS FPT2 test
Published in Journal of nuclear materials (01-10-2014)“…One objective of the FPT2 test of the PHEBUS FP Program was to study the degradation of an irradiated UO2 fuel bundle and the fission product behaviour under…”
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Fission-product behaviour in irradiated TRISO-coated particles: Results of the HFR-EU1bis experiment and their interpretation
Published in Journal of nuclear materials (01-08-2011)“…► The microstructure and FPs in UO 2 TRISO particles (10% FIMA, 1573 K) were studied. ► Very large porosities (>10 μm) were observed in the high temperature…”
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Contribution to the description of the absorber rod behavior in severe accident conditions: An experimental investigation of the Ag–Zr phase diagram
Published in Journal of nuclear materials (01-10-2015)“…Most pressurized water reactor (PWR) absorber rods are composed of an Ag–In–Cd (SIC) alloy inside a stainless steel (SS) cladding, themselves inserted into a…”
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14
Oxidation effects during corium melt in-vessel retention
Published in Nuclear engineering and design (15-08-2016)“…•Corium–steel interaction tests were re-examined particularly for transient processes.•Oxidation of corium melt was sensitive to oxidant supply and surface…”
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Adaptation of the ASTEC code system to accident scenarios in fusion installations
Published in Fusion engineering and design (01-10-2013)“…► IRSN has a first version of ASTEC able to model an accident in ITER. ► Models are developed to make possible water/air ingress simulations in the vessel. ►…”
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Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention
Published in Nuclear engineering and design (01-02-2018)“…•Simple equations for temperature gradients in liquid-solid systems are given.•The models are compared with data from METCOR, METCOR-P, MASCA projects.•A model…”
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Progress in understanding fission-product behaviour in coated uranium-dioxide fuel particles
Published in Journal of nuclear materials (31-03-2009)“…Supported by results of calculations performed with two analytical tools (MFPR, which takes account of physical and chemical mechanisms in calculating the…”
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18
Theoretical investigation on the point defect formation energies in beryllium and comparison with experiments
Published in Nuclear materials and energy (01-08-2017)“…•DFT investigations dedicated to the hcp beryllium.•An experimental value of vacancy formation energy is proposed on the basis of a critical…”
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Fission product release in the first two PHEBUS tests FPT0 and FPT1
Published in Nuclear engineering and design (01-09-2005)“…The fission product (FP) behaviour in PHEBUS FPT0 (fresh fuel rods) and FPT1 (irradiated fuel) in-pile experiments is interpreted. The main experimental…”
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Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2
Published in Annals of nuclear energy (01-12-2014)“…•MCCI research in SARNET2 consisted of large & small-scale testing & modelling.•Heavy (U,Zr)O2 melt interacts with light concrete oxide to produce multiple,…”
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