Tungsten has been proposed for use in the divertor of future fusion devices. In this environment, it will be exposed to high heat fluxes, neutron damage and hydrogen and helium implantation. This review covers previous experimental and modelling work to establish our ability to predict the performance of tungsten in a fusion environment. Surrogates for high-energy neutrons have been used to predict the change in mechanical properties of tungsten, including fission neutron and self-ion exposure. These studies are critically analysed, with a focus on the difference in results from neutron and ion studies. Further studies to improve our ability to predict the performance of tungsten are proposed as a critical part of the path towards a working...
The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based o...
Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, s...
Abstract Tungsten is a candidate material for a protective armour on the plasma-facing first wall of...
Tungsten has been proposed for use in the divertor of future fusion devices. In this environment, it...
Tungsten will be a key material for the plasma-facing components in future fusion devices. Its mecha...
Tungsten will be a key material for the plasma-facing components in future fusion devices. Its mecha...
Neutron damage is a major deciding factor in the commercialisation of a fusion power plant. Neutron ...
AbstractThe paper presents the development of experimental investigations and recent results of the ...
In nuclear fusion devices the surfaces directly facing the plasma are irradiated with high energy fl...
In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particl...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is being considered as a potential plasma-facing material for future fusion devices, primar...
The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based o...
Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, s...
Abstract Tungsten is a candidate material for a protective armour on the plasma-facing first wall of...
Tungsten has been proposed for use in the divertor of future fusion devices. In this environment, it...
Tungsten will be a key material for the plasma-facing components in future fusion devices. Its mecha...
Tungsten will be a key material for the plasma-facing components in future fusion devices. Its mecha...
Neutron damage is a major deciding factor in the commercialisation of a fusion power plant. Neutron ...
AbstractThe paper presents the development of experimental investigations and recent results of the ...
In nuclear fusion devices the surfaces directly facing the plasma are irradiated with high energy fl...
In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat and particl...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors (NFR...
Tungsten is being considered as a potential plasma-facing material for future fusion devices, primar...
The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based o...
Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, s...
Abstract Tungsten is a candidate material for a protective armour on the plasma-facing first wall of...