International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the nuclear fuel in the future high-temperature gas cooled nuclear reactors. In such a harsh environment, SiC will be submitted to energetic particles giving rise to atomic displacements which can alter its retention capability for the fission products. The aim of the present work is to examine the effects induced by the implantation of a typical fission product, namely iodine (I), into SiC at different temperatures and to study its diffusion behaviour under temperature and ion post-irradiation. Ion implantations at 400 or 600 °C produce significantly less damage than implantation at room temperature followed by subsequent thermal annealing. In a...
Silicon carbide is envisaged as a cladding material for the nuclear fuel in the fourth generation re...
Abstract. Diffusion of silver and iodine through polycrystalline SiC layers produced by PBMR (Pty) L...
The effect of ion irradiation and annealing on the microstructure and migration behaviour of implant...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is a potential cladding material for advanced nuclear fu...
International audienceSilicon carbide (SiC) is a potential cladding material for advanced nuclear fu...
International audienceSilicon carbide (SiC) is a potential cladding material for advanced nuclear fu...
Silicon carbide is envisaged as a cladding material for the nuclear fuel in the fourth generation re...
Silicon carbide is envisaged as a cladding material for the nuclear fuel in the fourth generation re...
Abstract. Diffusion of silver and iodine through polycrystalline SiC layers produced by PBMR (Pty) L...
The effect of ion irradiation and annealing on the microstructure and migration behaviour of implant...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is anticipated as a potential cladding material for the ...
International audienceSilicon carbide (SiC) is a potential cladding material for advanced nuclear fu...
International audienceSilicon carbide (SiC) is a potential cladding material for advanced nuclear fu...
International audienceSilicon carbide (SiC) is a potential cladding material for advanced nuclear fu...
Silicon carbide is envisaged as a cladding material for the nuclear fuel in the fourth generation re...
Silicon carbide is envisaged as a cladding material for the nuclear fuel in the fourth generation re...
Abstract. Diffusion of silver and iodine through polycrystalline SiC layers produced by PBMR (Pty) L...
The effect of ion irradiation and annealing on the microstructure and migration behaviour of implant...