This paper presents the last results obtained in the ITER First Wall (FW) development work programme performed in Europe on beryllium (Be), copper (Cu) alloys and 316L(N) stainless steel (SS) joining by Hot Isostatic Pressing (HIPping). It reports first the performances under high heat flux testing of CuCrZr/316L(N) SS mock-ups and compares them with those obtained earlier with CuAl25/316L(N) SS mock-ups. It reports then the results of the last developments done on Be/Cu alloy HIPped joints. In particular it presents the results of high heat flux testing of Be/CuCrZr FW mock-ups and compares them with those obtained earlier with Be/CuAl25 FW mock-ups. It gives the status of on-going thermal fatigue tests of Be/Cu alloy FW mock-ups and prese...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
AbstractPaper introduces thermal fatigue testing devices, developed and operated under fusion-relate...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...
This paper presents the main achievements of the European Home Team (EU HT) test programme of ITER p...
This paper presents the main achievements of the European Home Team (EU HT) test programme of ITER p...
In recent years, material development for ITER blanket components has been fervent; yet, a lack of m...
The First Wall panels for ITER are complex parts composed of stainless steel, copper and beryllium [...
In recent years, material development for ITER blanket components has been fervent; yet, a lack of m...
An overview is given of the wide range of activities contained within recent R&D being performed...
The ITER first wall (FW) panel consists of beryllium in the form of tiles covering its surface, high...
An overview is given of the wide range of activities contained within recent R&D being performed...
A research and development (R&D) programme for the ITER blanket-shield modules has been implemen...
In this paper, progress in the high heat flux (HHF) qualification testing of TGP-56FW beryllium grad...
A research and development (R&D) programme for the ITER blanket-shield modules has been implemen...
This paper describes the main activities carried out in the frame of EU-DA prequalification for the ...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
AbstractPaper introduces thermal fatigue testing devices, developed and operated under fusion-relate...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...
This paper presents the main achievements of the European Home Team (EU HT) test programme of ITER p...
This paper presents the main achievements of the European Home Team (EU HT) test programme of ITER p...
In recent years, material development for ITER blanket components has been fervent; yet, a lack of m...
The First Wall panels for ITER are complex parts composed of stainless steel, copper and beryllium [...
In recent years, material development for ITER blanket components has been fervent; yet, a lack of m...
An overview is given of the wide range of activities contained within recent R&D being performed...
The ITER first wall (FW) panel consists of beryllium in the form of tiles covering its surface, high...
An overview is given of the wide range of activities contained within recent R&D being performed...
A research and development (R&D) programme for the ITER blanket-shield modules has been implemen...
In this paper, progress in the high heat flux (HHF) qualification testing of TGP-56FW beryllium grad...
A research and development (R&D) programme for the ITER blanket-shield modules has been implemen...
This paper describes the main activities carried out in the frame of EU-DA prequalification for the ...
Beryllium as the plasma facing material for the first wall of ITER will be exposed to thermal, parti...
AbstractPaper introduces thermal fatigue testing devices, developed and operated under fusion-relate...
AbstractBeryllium as the plasma facing material for the first wall of ITER will be exposed to therma...