A tritium permeation 'short cut' for plasma-facing components of fusion reactors
A tritium permeation 'short cut' for plasma-facing components of fusion reactors
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聚变反应堆面向等离子体组件的氚渗透“捷径”
DOI：
10.1088/1741-4326/aaefd0
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发表时间：
2019
期刊：
影响因子：
3.3
通讯作者：
Luo Guang-Nan
中科院分区：
文献类型：
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作者：
Zhou Hai-Shan;Liu Hao-Dong;Wang Lu;Yang Xin;Oya Yasuhisa;Zhao Ming-Zhong;Tanabe Tetsuo;Xu Yu-Ping;Yuan Xiao-Gang;Li Bo;Ding Fang;Luo Guang-Nan
在ITER等聚变反应堆中，面向等离子体的部件（PFC）将受到强等离子体/中性流的作用，从而引起氚（T）的渗透问题。在目前的工作中，第一个的一类实验氢同位素（D）通过ITER的PFC模拟传输已被证明在线性等离子体设施。将具有0.5 mm间隙的8 mm厚W瓷砖安装在结构材料上并暴露于D等离子体。间隙和磁场线之间的角度被设置为5 °，以确保W后面的结构材料不暴露于来自等离子体的带电D离子。当等离子体启动时，发现样品模型在几十秒内被D穿透，这表明D可以穿透PFC的热沉而不穿过厚的W装甲，即间隙充当氢同位素泄漏“捷径”。为了对这些材料的渗透通量进行直接比较，还进行了通过W和结构材料的直接D等离子体驱动渗透（PDP）实验。通过结构材料测得的渗透D通量被发现是数量级高于W，表明T运输从PFCs的间隙可能有助于在反应堆中的总泄漏的显着部分。在本文的后半部分，提出了一种解决渗透问题的方法。
In ITER and other fusion reactors, plasma-facing components (PFCs) will be subjected to intense plasma/neutral fluxes and tritium (T) permeation issue will be raised. In the present work, first-of-a-kind experiments on hydrogen isotope (D) transport through ITER-like PFC mock-ups have been demonstrated in a linear plasma facility. 8 mm thick W tiles with 0.5 mm gaps are installed on structural materials and exposed to D plasmas. The angle between the gaps and the magnetic field line is set to be 5 to ensure the structural materials behind W are not exposed to charged D ions from plasma. When plasma is started up, the sample mock-ups are found to be penetrated by D within tens of seconds, suggesting that D can penetrate through heat sink of PFCs without passing through the thick W armor, ie the gaps act as a hydrogen isotope leakage'short cut'. To make a straightforward comparison of permeation flux for these materials, direct D plasma-driven permeation (PDP) experiments through W and structural materials are performed as well. The measured permeated D fluxes through structural materials are found to be orders of magnitude higher than that of W, indicating T transport from the gaps of PFCs may contribute a remarkable fraction of total leakage in reactors. In the latter part of this paper, a solution to address the permeation issue is proposed.