Search Results - "Barrachin, M."

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  1. 1

    Morphology and phase distributions of molten core in a reactor vessel by Song, JinHo, An, SangMo, Kim, Jong-Yun, Barrachin, M., Piar, B., Michel, B.

    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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  2. 2

    Diffusivity of hydrogen and properties of point defects in beryllium investigated by DFT by Ferry, L., Virot, F., Ferro, Y., Matveev, D., Linsmeier, Ch, Barrachin, M.

    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. 3

    Hafnium oxidation at high temperature in steam by Guilbert-Banti, S., Viretto, A., Barrachin, M., Tanguy, C., Steinbrück, M., Stuckert, J.

    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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  4. 4

    A comparison of core degradation phenomena in the CORA, QUENCH, Phébus SFD and Phébus FP experiments by Haste, T., Steinbrück, M., Barrachin, M., de Luze, O., Grosse, M., Stuckert, J.

    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. 5

    Contribution to a better evaluation of the dust speciation in case of an accident in ITER by Virot, F., Ferry, L., Ferro, Y., Pardanaud, C., Barrachin, M.

    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. 6

    Experimental study and thermodynamic modelling of the Ag-Cd-In system by Fischer, E., Gajavalli, K., Mikaelian, G., Benigni, P., Rogez, J., Decreton, A., Barrachin, M.

    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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  7. 7

    Progress on source term evaluation of accidental events in the experimental fusion installation ITER by Virot, F., Barrachin, M., Vola, D.

    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. 8

    Critical evaluation of experimental data of solution enthalpy of zirconium in liquid aluminum by Barrachin, M., Gajavalli, K., Decreton, A., Virot, F., Bénigni, P., Rogez, J., Mikaelian, G., Fischer, E., Lomello-Tafin, M., Antion, C., Janghorban, A.

    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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  9. 9

    Enthalpy of mixing in the Ag-Cd-In ternary liquid phase by Benigni, P., Hassam, S., Decreton, A., Mikaelian, G., Gajavalli, K., Barrachin, M., Fischer, E., Rogez, J.

    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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  10. 10

    Theoretical prediction of thermodynamic properties of tritiated beryllium molecules and application to ITER source term by Virot, F., Barrachin, M., Souvi, S., Cantrel, L.

    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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  11. 11

    Fuel and fission product behaviour in early phases of a severe accident. Part II: Interpretation of the experimental results of the PHEBUS FPT2 test by Dubourg, R., Barrachin, M., Ducher, R., Gavillet, D., De Bremaecker, A.

    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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  12. 12

    Fission-product behaviour in irradiated TRISO-coated particles: Results of the HFR-EU1bis experiment and their interpretation by Barrachin, M., Dubourg, R., de Groot, S., Kissane, M.P., Bakker, K.

    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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  13. 13

    Contribution to the description of the absorber rod behavior in severe accident conditions: An experimental investigation of the Ag–Zr phase diagram by Decreton, A., Benigni, P., Rogez, J., Mikaelian, G., Barrachin, M., Lomello-Tafin, M., Antion, C., Janghorban, A., Fischer, E.

    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. 14

    Oxidation effects during corium melt in-vessel retention by Almyashev, V.I., Granovsky, V.S., Khabensky, V.B., Krushinov, E.V., Sulatsky, A.A., Vitol, S.A., Gusarov, V.V., Bechta, S., Barrachin, M., Fichot, F., Bottomley, P.D., Fischer, M., Piluso, P.

    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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  15. 15

    Adaptation of the ASTEC code system to accident scenarios in fusion installations by Séropian, C., Barrachin, M., Van Dorsselaere, J.P., Vola, D.

    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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  16. 16

    Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention by Khabensky, V.B., Granovsky, V.S., Almjashev, V.I., Vitol, S.A., Krushinov, E.V., Kotova, S.Ju, Sulatsky, A.A., Gusarov, V.V., Bechta, S.V., Barrachin, M., Bottomley, D., Fischer, M., Hellmann, S., Piluso, P., Miassoedov, A., Tromm, W.

    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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  17. 17

    Progress in understanding fission-product behaviour in coated uranium-dioxide fuel particles by Barrachin, M., Dubourg, R., Kissane, M.P., Ozrin, V.

    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. 18

    Theoretical investigation on the point defect formation energies in beryllium and comparison with experiments by Ferry, L., Virot, F., Barrachin, M., Ferro, Y., Pardanaud, C., Matveev, D., Wensing, M., Dittmar, T., Koppen, M., Linsmeier, C.

    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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  19. 19

    Fission product release in the first two PHEBUS tests FPT0 and FPT1 by Dubourg, R., Faure-Geors, H., Nicaise, G., Barrachin, M.

    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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  20. 20

    Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2 by Bakardjieva, S., Barrachin, M., Bechta, S., Bezdicka, P., Bottomley, D., Brissonneau, L., Cheynet, B., Dugne, O., Fischer, E., Fischer, M., Gusarov, V., Journeau, C., Khabensky, V., Kiselova, M., Manara, D., Piluso, P., Sheindlin, M., Tyrpekl, V., Wiss, T.

    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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