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Qualification tests of Beryllium components for ITER

Beryllium (Be) is one of the most interesting materials to be used as plasma facing material for the first wall of ITER. This is reasoned by its promising material properties, e.g. the good plasma compatibility, relatively high thermal conductivity, its high affinity to oxygen (“oxygen getter”), as well as the low activation potential. However, testing of beryllium components is quite challenging because of its toxicity and the required safety procedures. The aim of the current research activities is the detection of damages at the interfaces between armour and heat sink material (Beryllium and CuCrZr) after a high number of cyclic thermal loads.

European Beryllium mock up for first wall qualification tests for ITERFigure 1: European Beryllium mock up for first wall qualification tests for ITER

High heat flux thermal fatigue tests are carried out at FZJ. We are part of the first phase of the qualification program of the Domestic Agencies (DAs) for the procurement of the First Wall of ITER. In total, five different mock ups (figure 1) were tested successfully under transient MARFE (Multifaceted Axisymmetric Radiation from the Edge) loading conditions in the electron beam facility JUDITH 2 at 1.75 MW/m² for 10 s and 1000 cycles. In addition 100 cycles at higher power densities were carried out. The temperature evolution of the beryllium surface during the qualification tests is monitored continuously by using an infrared thermos-camera (FLIR SC6000). An example of the temperature distribution is shown in figure 2.

Infrared image at the end of the 1200th cycle (2.75 MW/m2, ? = 0.25)Figure 2: Infrared image at the end of the 1200th cycle (2.75 MW/m2, ? = 0.25)


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