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Surface Modification and Deuterium Retention in Tungsten and Molybdenum Exposed to Low-Energy, High Flux Deuterium Plasmas

机译:钨和钼暴露于低能量,高通量氘质等离子体的表面改性和氘保留

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Deuterium retention in single crystal and polycrystalline tungsten and molybdenum exposed to low-energy (38-200 eV/D), high ion flux (10{sup}21-10{sup}22 D/m{sup}2s) deuterium plasmas at various temperatures were examined with the D({sup}3He,p) {sup}4He nuclear reaction at a 3He energy varied from 0.69 to 4.0 MeV, and with thermal desorption spectroscopy. The surface morphology was examined by scanning electron microscope. Blisters formed on the Mo surfaces under plasma exposure are significantly larger in size than those for W. The D retention in the W and Mo samples increases with the exposure temperature, reaching its maximum at about 500 and 530 K (for ion fluxes of 10{sup}21 and 10{sup}22 D/m{sup}2/s), respectively, and then decreases as the temperature grows further. For polycrystalline W and Mo exposed at temperatures above 400 K, the D retention in the bulk (far beyond the ion implanted zone) is dominant. Plastic deformation caused by deuterium super-saturation within the near-surface layer is suggested as a mechanism for blister formation and creation of defects responsible for deuterium trapping at depths up to several micrometers.
机译:在单晶和多晶钨和钼暴露于低能量(38-200伏特/ d),高的离子通量氘保持率(10 {SUP} {21-10} SUP 22 d /米{SUP} 2S)氘等离子体在各种温度下与d({SUP}的3He,p)的{} SUP在的3He能量变化从0.69至4.0兆电子伏4He的核反应,并用升温脱附法进行了研究。表面形态用扫描电子显微镜检查。形成在沫水泡等离子体暴露面下的尺寸比那些在与曝光温度W和Mo增加的样品W的d保留显著更大,在10约500至530 K(用于离子通量{达到其最大SUP} 21和10 {SUP} 22 d /米{SUP} 2 / s)的,分别,然后随着温度的进一步增长。多晶W和Mo裸露在温度高于400 K,在本体(远远超出了离子注入区)的d保留是主要的。引起的近表面层内氘超饱和塑性变形建议作为在深度达数微米泡罩形成和负责氘俘获缺陷创建的机构。

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