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The present volume of Atomic and Plasma–Material Interaction Data for Fusion presents the results of a coordinated research project (CRP) on plasma-wall interaction with irradiated tungsten and tungsten alloys in fusion devices. The chemical element tungsten is widely foreseen as a plasma-facing material in a fusion reactor, where it is subject to an intense neutron radiation flux. This publication provides details of a 5-year project devoted to better understanding the properties of tungsten in this environment through experimental study and theoretical modelling. Of particular practical concern is the viability of the metal as a structural material after irradiation damage, and its increased propensity to absorb the tritium fuel used in a fusion reaction.
The present volume of Atomic and Plasma–Material Interaction Data for Fusion presents the results of a coordinated research project (CRP) on plasma-wall interaction with irradiated tungsten and tungsten alloys in fusion devices. The chemical element tungsten is widely foreseen as a plasma-facing material in a fusion reactor, where it is subject to an intense neutron radiation flux. This publication provides details of a 5-year project devoted to better understanding the properties of tungsten in this environment through experimental study and theoretical modelling. Of particular practical concern is the viability of the metal as a structural material after irradiation damage, and its increased propensity to absorb the tritium fuel used in a fusion reaction.