Abstract

Studies of samples of graphite heat-shielding facing of the T-15MD tokamak chamber with stationary plasma loads in the PLM plasma device and high-power electron beams simulating loads during ELMs and transient processes were carried out. When the graphite facing samples were tested with plasma loads up to 2 MW/m², their surface temperature reached more than 1200°C, the surface heating did not lead to cracking, a change in the relief, or significant erosion of the graphite surface. The plasma action led to the growth of a layer of highly porous carbon structures on the surface in the zone of contact with the plasma column. Irradiation of graphite with electron beams with a load of less than 12 MW/m² did not lead to changes in the surface structure; at a load exceeding 24 MW/m², the processes of erosion and cracking of the surface along the grain boundaries began. At thermal cyclic loads exceeding 380 MW/m², effects of significant erosion were observed with a rate of material removal from the graphite surface up to 175 μm/s. The conducted experimental studies and tests are considered as the basis for using the investigated type of graphite as the facing of heat-shielding components of the divertor and the first wall for operation in the T-15MD tokamak.

中文翻译：

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通过 PLM 装置中的稳态等离子体负载和强大的电子束研究 T-15MD 托卡马克的保护性面向等离子体的石墨容器内组件

摘要

对 T-15MD 托卡马克室的石墨隔热面样品进行了研究，该样品具有 PLM 等离子体装置中的固定等离子体负载和高功率电子束模拟 ELM 和瞬态过程中的负载。当石墨饰面样品在高达 2 MW/m ^{2 的}等离子体负载下进行测试时，其表面温度达到 1200°C 以上，表面加热没有导致石墨表面开裂、浮雕变化或显着侵蚀. 等离子体作用导致在与等离子体柱接触的区域的表面上生长出一层高度多孔的碳结构。用低于 12 MW/m ²负载的电子束照射石墨不会导致表面结构发生变化；负载超过 24 MW/m²，沿晶界的表面侵蚀和开裂过程开始。在超过 380 MW/m ^{2 的}热循环负载下，观察到显着侵蚀的影响，石墨表面的材料去除速率高达 175 μm/s。所进行的实验研究和测试被认为是使用所研究的石墨类型作为偏滤器的隔热部件的表面和 T-15MD 托卡马克操作的第一壁的基础。