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首页> 外文期刊>Nuclear Materials and Energy >In-operando observation of helium-irradiation ion effects on surface deuterium retention through LiOH bonding in lithium films on tungsten substrates
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In-operando observation of helium-irradiation ion effects on surface deuterium retention through LiOH bonding in lithium films on tungsten substrates

机译:操作中观察氦辐照离子通过钨基体上锂膜中的LiOH键对表面氘保留的影响

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The plasma surface interactions within a fusion device are one of the limiting factors to long pulse, power generating operation. A plasma facing component material will require effective heat tolerance, minimal erosion yield, and minimal fuel retention properties. Tungsten (W) has been selected as the divertor material for the International Thermonuclear Experimental Reactor (ITER) due to its high thermal conductivity and high sputter threshold. However, when W is exposed to high particle flux (>1022ions/m2s) at high surface temperatures (>600?°C), the surface will develop defects such as pits, blisters, and nano-structured tendrils, reducing the beneficial properties of W. To overcome this limitation, a more radiation tolerant thin film material could be used, such as lithium (Li). In addition, the lithium film can protect the plasma from high-Z W sputtered atoms. In multiple tokamak devices, a Li wall coating, has improved the plasma performance by reducing fuel recycling from the walls, stabilizing the edge plasma and decreasing the number of edge localized modes (ELMs). Since ELMs help eject impurities from the core plasma, the complete suppression of ELMs is detrimental. Methods to regulate the frequency of ELMs have been investigated using gas puffs. In this work we report a new method to control the ELM frequency by tuning fuel recycling via the intrinsic helium (He) ions produced as ash from the deuterium (D) – tritium (T) fusion reaction. In Li films, one mechanism to retain D is via a chemical interaction between Li, O (oxygen), and D. Previous work has shown that when He ions are introduced with D ions, in a dual beam irradiation of Li films on W, a reduction in the dynamic surface D retention is observed. To further investigate this phenomenon, 1–2 um films of Li on W were exposed to sequential irradiations of D and He. The He fluence was ≈5% of the D (3.3?×?1020ions/m2). The energies for the He and D ions were 1000?eV and 250?eV/amu, respectively and samples were exposed at room temperature. The surface chemistry was characterized with x-ray photoelectron spectroscopy (XPS) to determine changes in retention. The XPS scans were conductedin-situandin-operandofor the irradiations. Our results showed a decrease in the surface retention when He follows D ions and little change in the retention when D follows He. This indicates that He breaks the D retention mechanism in Li.
机译:聚变装置内的等离子体表面相互作用是长脉冲发电操作的限制因素之一。面对等离子体的部件材料将需要有效的耐热性,最小的腐蚀产量和最小的燃料保持性能。钨(W)由于其高导热性和高溅射阈值而被选为国际热核实验反应堆(ITER)的分流器材料。但是,当W在较高的表面温度(> 600?C)下暴露于高粒子通量(> 1022ions / m2s)时,表面将形成缺陷,例如凹坑,水泡和纳米结构的卷须,从而降低了W的有益性能。为了克服此限制,可以使用耐辐射性更高的薄膜材料,例如锂(Li)。另外,锂膜可以保护等离子体免受高Z W溅射原子的侵害。在多个托卡马克装置中,锂壁涂层通过减少壁的燃料再循环,稳定边缘等离子体并减少边缘局部模式(ELM)的数量,提高了等离子体性能。由于ELM有助于从核心等离子体中喷射出杂质,因此完全抑制ELM是有害的。已经研究了使用抽气来调节ELM频率的方法。在这项工作中,我们报告了一种新的方法,该方法通过利用氘(D)-((T)聚变反应产生的灰分形式的固有氦(He)离子来调节燃料循环,从而控制ELM频率。在Li膜中,保留D的一种机制是通过Li,O(氧)和D之间的化学相互作用。先前的工作表明,当He离子与D离子一起引入时,在W上对Li膜进行双束照射时,观察到动态表面D保留的减少。为了进一步研究这种现象,将W上的1-2 um的Li膜暴露于D和He的连续照射下。 He通量约为D的5%(3.3?×?1020ions / m2)。 He和D离子的能量分别为1000?eV和250?eV / amu,样品在室温下暴露。用X射线光电子能谱(XPS)表征表面化学性质,以确定保留率的变化。 XPS扫描是在原位和操作数下进行的。我们的结果表明,当He跟随D离子时,表面保留率降低,而当D跟随He时,保留率几乎没有变化。这表明他打破了李中的D保留机制。

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