Beryllium (Be) co-deposition with hydrogen isotopes will probably be the main mechanism of tritium accumulation in ITER. To reduce the use of baking of the first wall and divertor, raising strike-points during a pure deuterium (D) discharge has been proposed to heat the co-deposits directly and enhance tritium desorption. The feasibility of such plasma-induced removal as a potential means of tritium control has been investigated. Be-D co-deposited layers with a thickness of around 3 μm were created at 428–458 K and exposed to D or H plasma at various temperatures (673–873 K) for various times (180–1200 s). The remaining D content was measured by thermal desorption spectroscopy and compared to the control samples. Plasma-induced desorption was found to be efficient in removing significant amounts of D out of the co-deposits, removing 85% of D from the layer after D plasma exposure at 773 K for 1200 s and 84% of D after exposure at 873 K for only 180 s.

铍与氢同位素共沉积可能是ITER中accumulation积累的主要机理。为了减少第一壁和分流器的烘烤，提出了在纯氘（D）放电过程中提高击穿点以直接加热共沉积物并增强tri解吸的方法。已经研究了这种等离子体诱导的去除作为control控制的潜在手段的可行性。在428–458 K时形成厚度约为3μm的Be-D共沉积层，并在不同温度（673–873 K）的不同时间（180–1200 s）暴露于D或H等离子体。剩余的D含量通过热解吸光谱法测量并与对照样品比较。发现血浆诱导的解吸可以有效地从共沉积物中去除大量D，