ITER first wall (FW) panels are irradiated by energetic neutrons during the nuclear phase. Thus, an irradiation and high heat flux testing programme is undertaken by the ITER organization in order to evaluate the effects of neutron irradiation on the performance of enhanced heat flux (EHF) FW components. The test campaign includes neutron irradiation (up to 0.6–0.8 dpa at 200 °C–250 °C) of mock-ups that are representative of the final EHF FW panel design, followed by thermal fatigue tests (up to 4.7 MW m−2). Mock-ups were manufactured by the same manufacturing process as proposed for the series production. After a pre-irradiation thermal screening, eight mock-ups will be selected for the irradiation campaigns. This paper reports the prepara...
This paper presents the last results obtained in the ITER First Wall (FW) development work programme...
For the second qualification of the First Wall (FW) procurement of the International Thermonuclear E...
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma ...
A broad spectrum of high heat flux test facilities are being used worldwide to investigate the therm...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...
During the operation of ITER, the plasma facing components will undergo different kinds of thermal l...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
In order to study the influence of fast neutrons on the behaviour of high heat flux components for I...
This paper describes the main activities carried out in the frame of EU-DA prequalification for the ...
The development of plasma facing components for next step fusion devices in Europe is strongly focus...
The ITER first wall (FW) panel consists of beryllium in the form of tiles covering its surface, high...
In this paper, progress in the high heat flux (HHF) qualification testing of TGP-56FW beryllium grad...
According to the increased heat flux condition up to 5 MW/m(2) in the International Thermonuclear Ex...
With the aim to assess the option to start the ITER operation with a full tungsten divertor, an R&D ...
This paper presents the last results obtained in the ITER First Wall (FW) development work programme...
For the second qualification of the First Wall (FW) procurement of the International Thermonuclear E...
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma ...
A broad spectrum of high heat flux test facilities are being used worldwide to investigate the therm...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...
During the operation of ITER, the plasma facing components will undergo different kinds of thermal l...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
In order to study the influence of fast neutrons on the behaviour of high heat flux components for I...
This paper describes the main activities carried out in the frame of EU-DA prequalification for the ...
The development of plasma facing components for next step fusion devices in Europe is strongly focus...
The ITER first wall (FW) panel consists of beryllium in the form of tiles covering its surface, high...
In this paper, progress in the high heat flux (HHF) qualification testing of TGP-56FW beryllium grad...
According to the increased heat flux condition up to 5 MW/m(2) in the International Thermonuclear Ex...
With the aim to assess the option to start the ITER operation with a full tungsten divertor, an R&D ...
This paper presents the last results obtained in the ITER First Wall (FW) development work programme...
For the second qualification of the First Wall (FW) procurement of the International Thermonuclear E...
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma ...