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1. Introduction The safety issues associated with tokamak dust include radiological hazard (tritium and activation products), toxicity, and chemical reactivity with steam and air [1,2,3]. , cannot be mobilised). Dust will be produced and accumulated inside the ITER-FEAT Vacuum Vessel during operation as a result of erosion of plasma-facing components (PFC). Since the main armor materials are Be (first wall), W (divertor) and C (divertor strike point), the ITER dust will be a composition of these elements.

From the ellipsometric parameters, the refraction and extinction indices for an oxygen-containing film before and after bombardment of the Be mirror by ions of deuterium plasma were obtained using the model shown in Figure 3. 54) a) b) Figure 3. Model of the sample: a) Be nonexposed and b) Be exposed . 32 6. Discussion We propose that the initial sharp drop of R(t) dependence is brought about by the transformation of the BeO film into a Be(OD)2 film due to the bombardment of the Be mirror by deuterium ions in accordance with the process described by equation (1.

2'10 15 ern") without titanium dopes. We also exclude a possible process of carbon hydrogen transport from a cylindrical heater made of POCO graphite to the sample placed inside the heater. This conclusion was made from the analysis of the sample surface structure by the method of electron diffraction on the reflection allowing the information to be obtained on the 5-10 nm surface layer of the material. On the RG-Ti-B sample exposed in D-atmosphere this layer consisted of a well-oriented large-crystalline graphite without visible traces of turbostratic pyrolitic precipitate.

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