M. Schwarz, G. Hache, P. Von, and . Hardt, PHEBUS FP: a severe accident research programme for current and advanced light water reactors, Nuclear Engineering and Design, vol.187, issue.1, pp.47-69, 1999.

R. A. Lorenz and M. F. Osborne, A summary of ORNL fission product release tests with recommended release rates and diffusion coefficients, 1995.

Z. Lui, D. S. Cox, R. S. Dickson, and P. Elder, A summary of CRL fission product release measurements from UO2 samples during post-irradiation annealing, 1983.

A. Hidaka, Outcome of VEGA Program on Radionuclide Release from Irradiated Fuel under Severe Accident Conditions, Journal of Nuclear Science and Technology, vol.48, issue.1, pp.85-102, 2011.

B. J. Lewis, R. Dickson, F. C. Iglesias, G. Ducros, and T. Kudo, Overview of experimental programs on core melt progression and fission product release behaviour, Journal of Nuclear Materials, vol.380, issue.1-3, pp.126-143, 2008.

J. P. Leveque, B. Andre, G. Ducros, G. L. Marois, and G. Lhiaubet, The HEVA experimental program, Nuclear Technology, vol.108, issue.1, pp.33-44, 1994.

Y. Pontillon, G. Ducros, and P. P. Malgouyres, Behaviour of fission products under severe PWR accident conditions VERCORS experimental programme-Part 1: General description of the programme, Nuclear Engineering and Design, vol.240, issue.7, pp.1843-1852, 2010.

Y. Pontillon and G. Ducros, Behaviour of fission products under severe PWR accident conditions: The VERCORS experimental programme-Part 2: Release and transport of fission gases and volatile fission products, Nuclear Engineering and Design, vol.240, issue.7, pp.1853-1866, 2010.

Y. Pontillon and G. Ducros, Behaviour of fission products under severe PWR accident conditions. The VERCORS experimental programme-Part 3: Release of low-volatile fission products and actinides, Nuclear Engineering and Design, vol.240, issue.7, pp.1867-1881, 2010.

B. Clement, The Phebus Fission Product and Source Term International Programmes, Proceedings of the Annual Meeting on Nuclear Technology -Jahrestagung Kerntechnik -Tagungsbericht Proceedings, 2006.

Y. Pontillon, E. Geiger, C. L. Gall, S. Bernard, A. Gallais-during et al., Fission products and nuclear fuel behavior under severe accident conditions -Part 1: Main lessons learnt from the first VERDON test, Journal of Nuclear Materials, Submitting

E. Geiger, C. L. Gall, A. Gallais-during, Y. Pontillon, J. Lamontagne et al., Fission products and nuclear fuel behavior under severe accident conditions -Part 2: Fuel behavior in the VERDON-1 sample, Journal of Nuclear Materials, Submitting

G. Ducros, S. Bernard, M. P. Ferroud-plattet, and O. Ichim, Use of Gamma spectrometry for measuring fission product releases during a simulated PWR severe accident: Application to the VERDON experimental program, pp.1-7, 2009.

A. Gallais-during, J. Bonnin, P. Malgouyres, S. Bernard, Y. Pontillon et al., VERDON Laboratory : Performances of the Experimental LWR Severe Accident Device and Fisrt Results of Fission Products Release on High Burn-up UO2 fuel, presented at the 21st International Conference Nuclear Energy for New Europe, Ljubjana, 2012.

A. Gallais-during, J. Bonnin, P. Malgouyres, S. Morin, S. Bernard et al., Performance and first results of fission product release and transport provided by the VERDON facility, Nuclear Engineering and Design, vol.277, pp.117-123, 2014.

G. Ducros, P. P. Malgouyres, M. Kissane, D. Boulaud, and M. Durin, Fission product release under severe accidental conditions: general presentation of the program and synthesis of VERCORS 1-6 results, Nuclear Engineering and Design, vol.208, issue.2, pp.191-203, 2001.

Y. Pontillon, J. Bonnin, E. Addes, J. Cochaud, J. Piquemal et al., Fission gas release under normal and off-normal conditions: New analytical device implemented at the CEA Cadarache," presented at the European Working Group "Hot Laboratories and Remote handling, Plenary Meeting, 2005.

H. Kleykamp, The chemical state of the fission products in oxide fuels, Journal of Nuclear Materials, vol.131, issue.2-3, pp.221-246, 1985.

K. Masumichi, S. Masakazu, and N. Kenji, Phase study on solid fission products, Ba, Sr and Zr in oxide fuel, Journal of Nuclear Materials, vol.51, issue.1, pp.90-94, 1974.

H. Kleykamp, The solubility of selected fission products in UO2 and (U, Pu)O2, Journal of Nuclear Materials, vol.206, issue.1, pp.82-86, 1993.

J. Spino and D. Papaioannou, Lattice parameter changes associated with the rimstructure formation in high burn-up UO2 fuels by micro X-ray diffraction, Journal of Nuclear Materials, vol.281, issue.2-3, pp.146-162, 2000.

L. Lynds, W. A. Young, J. S. Mohl, and G. G. Libowitz, X-Ray and Density Study of Nonstoichiometry in Uranium Oxides, Nonstoichiometric Compounds, vol.39, pp.58-65, 1963.

S. Yamanaka and K. Kurosaki, Thermophysical properties of Mo-Ru-Rh-Pd alloys, Journal of Alloys and Compounds, vol.353, issue.1-2, pp.269-273, 2003.

M. S. Veshchunov, V. D. Ozrin, V. E. Shestak, V. I. Tarasov, R. Dubourg et al., Development of the mechanistic code MFPR for modelling fission-product release from irradiated UO2 fuel, Nuclear Engineering and Design, vol.236, issue.2, pp.179-200, 2006.