Description
The present volume of Atomic and Plasma–Material Interaction Data for Fusion presents the results of a coordinated research project 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 five 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.
More Information on reusing IAEA copyright material.
Keywords
Atomic, Plasma, Material Interaction Data, CRP, Coordinated Research Project, Alloy, Irradiated Tungsten Foil, Fusion Reactor, Theoretical Modelling, Metal, Viability, Irradiation Damaged Tungsten, Tritium Fuel, Fusion Reaction, Radiation Damage, Experiments, Deuterium, Helium, TDS, Thermal Desorption Spectroscopy, Deuterium Retention, Hydrogen, Transport, Trapping, MD, Molecular Dynamics, TDE, Threshold Displacement Energy, Ion-Irradiation, Tungsten Samples, Helium Retention, Rhenium, SIAs, Self-Interstitial Atoms, Neutron Radiation Flux