Search Results - "Gueneau, C"

TAF-ID: An international thermodynamic database for nuclear fuels applications by Guéneau, C., Dupin, N., Kjellqvist, L., Geiger, E., Kurata, M., Gossé, S., Corcoran, E., Quaini, A., Hania, R., Smith, A.L., Piro, M.H.A., Besmann, T., Turchi, P.E.A., Dumas, J.C., Welland, M.J., Ogata, T., Lee, B.O., Kennedy, J.R., Adkins, C., Bankhead, M., Costa, D.

“…The Thermodynamics of Advanced Fuels – International Database (TAF-ID) was developed using the Calphad method to provide a computational tool to perform…”
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Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident by Geiger, E., Guéneau, C., Pontillon, Y., Corcoran, E.C.

“…The chemical behaviour of the main elements present in a PWR irradiated fuel sample (UO2 fuel, Zr from the Zircaloy-cladding, Pu, Np, and fission products such…”
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Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests by Germain, A., Sercombe, J., Riglet-Martial, C., Introïni, C., Noirot, L., Pontillon, Y., Maugis, Ph, Guéneau, C.

“…This paper presents simulations of the VERDON 1 and RT6 tests (temperature increase up to fuel-clad melting, oxidizing and/or reducing conditions within the…”
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Thermodynamic assessment of the rhodium-ruthenium-oxygen (Rh-Ru-O) system by Gossé, S., Bordier, S., Guéneau, C., Brackx, E., Domenger, R., Rogez, J.

“…Ruthenium (Ru) and rhodium (Rh) are abundant platinum-group metals formed during burn-up of nuclear fuels. Under normal operating conditions, Rh and Ru…”
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Thermodynamic investigations of fuel-cladding chemical interaction in U-5Fs and U-10Zr metallic fuels with the TAF-ID by Geiger, E., Guéneau, C., Corcoran, E.C., Piro, M.H.A.

“…Fuel-Cladding Chemical Interaction (FCCI) in metallic nuclear fuels is a key phenomenon that limits the maximum burn-up and operating power as it can cause…”
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Multi-scale structural investigation of uranium-plutonium mixed oxides (U1-yPuy)O2-x with high plutonium content by Desagulier, M-M., Martinez, J., Martin, P.M., Lebreton, F., Guéneau, C., Clavier, N.

“…Uranium-Plutonium mixed oxides U1-yPuyO2-x are considered as the reference fuels for Sodium-cooled Fast neutron Reactors (SFRs). Nevertheless, there is a lack…”
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Surface tension of cavitation bubbles by Bossert, Marine, Trimaille, I, Cagnon, L, Chabaud, B, Gueneau, C, Spathis, P, Wolf, P E, Rolley, E

“…We have studied homogeneous cavitation in liquid nitrogen and normal liquid helium. We monitor the fluid content in a large number of independent mesopores…”
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Thermodynamic assessment of the Fe-Te system. Part II: Thermodynamic modeling by Arvhult, C.-M., Guéneau, C., Gossé, S., Selleby, M.

“…A thermodynamic description of the Fe-Te system modeled via the Calphad method is proposed, based on data published in a preceding publication Part I:…”
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Behaviour of (U,Am)O$_2$ in oxidizing conditions: a high-temperature XRD study by Epifano, E., Vauchy, R., Lebreton, F., Joly, A., Guéneau, C., Valot, Ch, Martin, P.M.

“…Uranium–americium oxides U$_{1−y}$Am$_y$O$_{2±x}$ are currently investigated as possible transmutation targets for next generation nuclear reactors. In the…”
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Laser heating investigation of the high-temperature interaction between zirconium and UO2 by Quaini, A., Gossé, S., Guéneau, C., Soldi, L., Manara, D.

“…The present work aims to improve accuracy of solid/liquid transition temperatures in Zr-rich corner of the U-Zr-O ternary system, where no experimental data…”
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Thermodynamic assessment of the Fe-Te system. Part I: Experimental study by Arvhult, C.-M., Poissonnet, S., Menut, D., Gossé, S., Guéneau, C.

“…A thermodynamic description of the Fe-Te system needs to be developed in order to model internal corrosion by fission products in fuel pins of Generation IV…”
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Experimental studies and thermodynamic assessment of the Ba-Mo-O system by the CALPHAD method by Smith, A.L., Rutten, M., Herrmann, L., Epifano, E., Konings, R.J.M., Colineau, E., Griveau, J.-C., Guéneau, C., Dupin, N.

“…Thermodynamic measurements on BaMoO4, BaMoO3 and BaMo3O10 are reported, that served as input for the development of a thermodynamic model of the Ba-Mo-O system…”
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Melting behaviour of uranium-americium mixed oxides under different atmospheres by Epifano, E., Prieur, D., Martin, P.M., Guéneau, C., Dardenne, K., Rothe, J., Vitova, T., Dieste, O., Wiss, T., Konings, R.J.M., Manara, D.

“…•The very high melting temperatures of (U,Am)-oxides (T > 2500 K) were measured.•The effect of the oxidation on the melting behaviour was studied.•Extensive…”
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Thermodynamic modelling assessment of the ternary system Cs-Mo-O by Smith, A.L., Pham Thi, T.N., Guéneau, C., Dumas, J.-C., Epifano, E., van Burik, W., Dupin, N.

“…This work reports the thermodynamic modelling assessment of the rather complex Cs-Mo-O system, which is key for the understanding of fission products chemistry…”
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Recent advances in the study of the UO2–PuO2 phase diagram at high temperatures by Böhler, R., Welland, M.J., Prieur, D., Cakir, P., Vitova, T., Pruessmann, T., Pidchenko, I., Hennig, C., Guéneau, C., Konings, R.J.M., Manara, D.

“…Recently, novel container-less laser heating experimental data have been published on the melting behaviour of pure PuO2 and PuO2-rich compositions in the…”
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Investigation of the solid/liquid phase transitions in the U–Pu–O system by Fouquet-Métivier, P., Martin, P.M., Manara, D., Dardenne, K., Rothe, J., Fossati, P.C.M., Guéneau, C.

“…Mixed oxides of uranium and plutonium U1-yPuyO2-x are currently studied as reference fuel for Sodium-cooled Fast Reactors (SFRs). To predict the margin to fuel…”
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Fission products chemistry in simulated PWR fuel up to 2100°C: Experimental characterisation and TAF-ID modelling by Geiger, E., Guéneau, C., Alpettaz, T., Bonnet, C., Chatain, S., Tougait, O., Menut, D., Bellayer, S., Hunault, M.O.J.Y., Corcoran, E.C.

“…The capabilities of the Thermodynamic of Advanced Fuels – International Database (TAF-ID) for reproducing the chemical behaviour of irradiated nuclear fuel in…”
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Calphad thermodynamic description of some binary systems involving U by Berche, A., Dupin, N., Guéneau, C., Rado, C., Sundman, B., Dumas, J.C.

“…Within the framework of a complex Calphad thermodynamic database for the 4th generation nuclear fuels, called Fuelbase, the description of different binary…”
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The high-temperature heat capacity of the (Th,U)O2 and (U,Pu)O2 solid solutions by Vălu, S.O., Beneš, O., Manara, D., Konings, R.J.M., Cooper, M.W.D., Grimes, R.W., Guéneau, C.

“…The enthalpy increment data for the (Th,U)O2 and (U,Pu)O2 solid solutions are reviewed and complemented with new experimental data (400–1773 K) and many-body…”
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Thermodynamic assessment of the cesium–oxygen system by coupling density functional theory and CALPHAD approaches by Gueneau, C, Fleche, J-L

“…The thermodynamic properties of cesium oxides were calculated by combining ab initio calculations at 0K and a quasi-harmonic statistical thermodynamic model to…”
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