Laser ablation of graphite with near infrared microsecond pulses von Doualle, T., Reymond, M., Pontillon, Y., Gallais, L.

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High power continuous wave laser heating of graphite in a high temperature range up to 3800 K von Gallais, L., Vidal, T., Lescoute, E., Pontillon, Y., Rullier, J. L.

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MERARG Experimental Loop: A Forward Fitting Method for Fission Gas Release Analysis von Losfeld, J., Desgranges, L., Clement, S., Pontillon, Y.

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A laser-based system to heat nuclear fuel pellets at high temperature von Quintal, C. Cifuentes, Reymond, M., Fiorito, F., Martin, F., Pontillon, M., Richaud, J. C., Doualle, T., Pontillon, Y., Gallais, L.

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Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating von Vidal, T., Gallais, L., Faucheux, J., Capdevila, H., Sercombe, J., Pontillon, Y.

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Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident von Geiger, E., Guéneau, C., Pontillon, Y., Corcoran, E.C.

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Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests von Germain, A., Sercombe, J., Riglet-Martial, C., Introïni, C., Noirot, L., Pontillon, Y., Maugis, Ph, Guéneau, C.

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Corrigendum to “Simulation of reactivity initiated accident thermal transients on nuclear fuels with laser remote heating” von Vidal, T., Gallais, L., Faucheux, J., Capdevila, H., Sercombe, J., Pontillon, Y.

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Coupled modeling of irradiated fuel thermochemistry and gas diffusion during severe accidents von Germain, A., Sercombe, J., Riglet-Martial, C., Introïni, C., Noirot, L., Pontillon, Y., Maugis, Ph

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An experimental platform for real-time measurement of the deformation of nuclear fuel rod claddings submitted to thermal transients von Gallais, L., Burla, R., Martin, F., Richaud, J. C., Volle, G., Pontillon, M., Capdevila, H., Pontillon, Y.

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Modeling of fission product release during severe accidents with the fuel performance code ALCYONE von Germain, A., Sercombe, J., Riglet-Martial, C., Introïni, C., Noirot, L., Pontillon, Y., Maugis, Ph

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Fission products and nuclear fuel behaviour under severe accident conditions part 1: Main lessons learnt from the first VERDON test von Pontillon, Y., Geiger, E., Le Gall, C., Bernard, S., Gallais-During, A., Malgouyres, P.P., Hanus, E., Ducros, G.

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A high power laser facility to conduct annealing tests at high temperature von Minissale, M., Durif, A., Hiret, P., Vidal, T., Faucheux, J., Lenci, M., Mondon, M., Kermouche, G., Pontillon, Y., Grisolia, C., Richou, M., Gallais, L.

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Miscibility Gap in the U–Nd–O Phase Diagram: a New Approach of Nuclear Oxides in the Environment? von Desgranges, L, Pontillon, Y, Matheron, P, Marcet, M, Simon, P, Guimbretière, G, Porcher, F

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Fission products and nuclear fuel behaviour under severe accident conditions part 2: Fuel behaviour in the VERDON-1 sample von Geiger, E., Le Gall, C., Gallais-During, A., Pontillon, Y., Lamontagne, J., Hanus, E., Ducros, G.

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Using laser remote heating to simulate extreme thermal heat loads on nuclear fuels von Vidal, T., Gallais, L., Faucheux, J., Capdevila, H., Pontillon, Y.

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Fission gas release behaviour of a 103 GWd/tHM fuel disc during a 1200 °C annealing test von NOIROT, J, PONTILLON, Y, YAGNIK, S, TURNBULL, J. A, TVERBERG, T

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Fission products and nuclear fuel behaviour under severe accident conditions part 3: Speciation of fission products in the VERDON-1 sample von Le Gall, C., Geiger, E., Gallais-During, A., Pontillon, Y., Lamontagne, J., Hanus, E., Ducros, G.

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Fission product speciation in the VERDON-3 and VERDON-4 MOX fuels samples von Le Gall, C., Reboul, S., Fayette, L., Blay, T., Zacharie-Aubrun, I., Félines, I., Hanifi, K., Roure, I., Bienvenu, P., Audubert, F., Pontillon, Y., Hazemann, Jean-Louis

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MOX fuel microstructural evolution during the VERDON-3 and 4 tests von Le Gall, C., Reboul, S., Fayette, L., Blay, T., Zacharie-Aubrun, I., Félines, I., Hanifi, K., Roure, I., Bienvenu, P., Audubert, F., Pontillon, Y., Hazemann, Jean-Louis

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