Plasma tests of a tin capillary-porous system (CPS) were carried out on the PLM plasma device. This CPS is made similar to the lithium CPS used in experiments in tokamaks T-10, T-11M. The CPS system was immersed in the PLM plasma device and tested for 3 hours in a stationary helium discharge with plasma load of 1 MW / m2. The tin CPS has not damaged after such plasma load suggesting it as plasma facing component in fusion reactors and plasma engines.
Investigations of samples made of a graphite tile of the lining of the chamber of the T-15MD tokamak with plasma loads simulating the conditions in the peripheral and divertor plasma of a large T-15MD tokamak. When testing samples in a plasma installation PLM with plasma loads of 2 MW/m2 for more than 200 minutes, the surface temperature of the samples reached 1288 ° C. Plasma loading and heating of the surface within the specified limits does not lead to cracking change in the relief and graphite sputtering. The analysis of the morphology and structure of the surface was carried out using the methods of scanning electron microscopy of samples after thermal loads. Surface erosion is insignificant. Long-term plasma loads lead to the growth of a layer of porous carbon structures. The growth rate of structures does not exceed 1–2 μm/h at the maximum heating temperature of the samples and decreases 10 times at 800 ° C. Investigations of graphite samples in an electron-beam setup were carried out with a beam of accelerated 60 keV electrons, which simulates the effect on the graphite lining of the chamber of transient processes expected in the T-15MD tokamak, including ELMs. It is shown that the energy flux of 24 MW/m2 for electron irradiation should be recognized as a threshold for the destruction of the surface of graphite tiles.
Lithium capillary-porous system (CPS) as a mat between molybdenum grids fixed in a molybdenum module was tested in PLM plasma device for 3 hours in a steady state helium discharge with plasma parameters relevant to scrape-off-layer and divertor plasma of large tokamak. The plasma load on the CPS was of 1 MW / m2 led to surface heating up to 700 °C and vaporization of lithium to plasma. Lithium ions was registered by optical emission spectra from plasma. The redeposition of vaporized lithium was detected on the PLM in-vessel components. Inspections of CPS modules after plasma irradiation did not reveal any damage of molybdenum grids.
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