Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, particle and neutron loads. In the frame of the European qualification program for ITER, two HIPped beryllium small scale flat-tile mock-ups consisting of a steel support structure, a CuCrZr/Cu heat sink and two beryllium tiles on top were manufactured by CEA. One mock-up was exposed to neutron irradiation up to 0.75dpa in beryllium in the RBT-6 fission reactor at Dimitrovgrad, Russia, while the other one was kept as reference. Furthermore, an identical mock-up was produced in Russia by manufacturing via electron beam induced rapid brazing and also exposed to the same neutron irradiation conditions. For qualification, all three flat-tile mock-ups ...
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma ...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
This paper presents the last results obtained in the ITER First Wall (FW) development work programme...
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...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...
In this paper, progress in the high heat flux (HHF) qualification testing of TGP-56FW beryllium grad...
The ITER first wall (FW) panel consists of beryllium in the form of tiles covering its surface, high...
Beside carbon materials and tungsten, beryllium will play an important role as plasma facing materia...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
ITER first wall (FW) panels are irradiated by energetic neutrons during the nuclear phase. Thus, an ...
The rising global energy consumption requires a broad research and development approach in the field...
The rising global energy consumption requires a broad research and development approach in the field...
The selection of the armour materials for the plasma facing components (PFC) was one of the importan...
The experimental fusion reactor ITER, currently under construction in Cadarache, France, is transfer...
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma ...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
This paper presents the last results obtained in the ITER First Wall (FW) development work programme...
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...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...
In this paper, progress in the high heat flux (HHF) qualification testing of TGP-56FW beryllium grad...
The ITER first wall (FW) panel consists of beryllium in the form of tiles covering its surface, high...
Beside carbon materials and tungsten, beryllium will play an important role as plasma facing materia...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
ITER first wall (FW) panels are irradiated by energetic neutrons during the nuclear phase. Thus, an ...
The rising global energy consumption requires a broad research and development approach in the field...
The rising global energy consumption requires a broad research and development approach in the field...
The selection of the armour materials for the plasma facing components (PFC) was one of the importan...
The experimental fusion reactor ITER, currently under construction in Cadarache, France, is transfer...
The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma ...
The experimental fusion reactor ITER will apply beryllium as first wall armor material. In present f...
This paper presents the last results obtained in the ITER First Wall (FW) development work programme...