Managing the loads and stresses acting on the wall in fusion plants, especially themigration of materials as a consequence of erosion processes and lifetime constraints affecting wall components, will be among the factors deciding on the feasibility of building a fusion power plant for permanent operation. Managing wall loads and stresses in ITER, which initially will be run only in the pulsed mode, is important especially in the interest of high availability of the experiment. The article describes the current state of research into plasma wall interactions and, in particular, the approaches to solutions and the strategies pursued in European fusion research to optimize the availability of ITER. This topic encompasses materials problems; e...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
The first burning fusion plasma experiment based on the tokamak principle, international tokamak exp...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
The control of wall loads in fusion devices, in particular with respect to the life time limitations...
The control of wall loads in fusion devices, in particular with respect to the life time limitations...
The International Tokamak Experimental Reactor (ITER), the first burning fusion plasma experiment ba...
The first burning fusion plasma experiment based on the tokamak principle, international tokamak exp...
The decreasing availability of energy and concern about climate change necessitate the development o...
The decreasing availability of energy and concern about climate change necessitate the development o...
The major increase in discharge duration and plasma energy in a next-step DT fusion reactor will giv...
The interaction processes between the burning plasma and the first wall in a fusion reactor are dive...
The major increase in discharge duration and plasma energy in a next-step DT [deuterium-tritium] fus...
\u3cp\u3eThe provision of a particle and power exhaust solution which is compatible with first-wall ...
robust and which determine the ongoing fusion research in present devices. These issues are largely ...
This paper gives an overview about erosion and deposition processes in fusion machines. The underlyi...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
The first burning fusion plasma experiment based on the tokamak principle, international tokamak exp...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...
The control of wall loads in fusion devices, in particular with respect to the life time limitations...
The control of wall loads in fusion devices, in particular with respect to the life time limitations...
The International Tokamak Experimental Reactor (ITER), the first burning fusion plasma experiment ba...
The first burning fusion plasma experiment based on the tokamak principle, international tokamak exp...
The decreasing availability of energy and concern about climate change necessitate the development o...
The decreasing availability of energy and concern about climate change necessitate the development o...
The major increase in discharge duration and plasma energy in a next-step DT fusion reactor will giv...
The interaction processes between the burning plasma and the first wall in a fusion reactor are dive...
The major increase in discharge duration and plasma energy in a next-step DT [deuterium-tritium] fus...
\u3cp\u3eThe provision of a particle and power exhaust solution which is compatible with first-wall ...
robust and which determine the ongoing fusion research in present devices. These issues are largely ...
This paper gives an overview about erosion and deposition processes in fusion machines. The underlyi...
The provision of a particle and power exhaust solution which is compatible with first-wall component...
The first burning fusion plasma experiment based on the tokamak principle, international tokamak exp...
The interaction between the edge-plasma in a fusion reactor and the surrounding first-wall component...