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High Flux Helium Irradiation of Dispersion-Strengthened Tungsten Alloys and Effects of Heavy Metal Impurity Layer Deposition
Journal of Nuclear Materials ( IF 2.8 ) Pub Date : 2020-11-13 , DOI: 10.1016/j.jnucmat.2020.152672
E. Lang , A. Kapat , T.W. Morgan , J.P. Allain

Tungsten has been chosen as the plasma-facing material (PFM) for the divertor region in ITER and also a candidate PFM for future plasma-burning nuclear fusion reactors. During fusion device operation, PFMs will be exposed to low-energy He irradiation at high temperatures, resulting in sub-surface bubbles and surface morphology changes such as pores and fuzz. Carbide dispersion-strengthened W materials may enhance the ductility of W, but their behavior under high flux He irradiation remains unclear. In this work, the response of dispersion-strengthened tungsten materials to high flux, low energy He irradiation at high temperature is examined. Tungsten alloyed with 1, 5, or 10 wt. % tantalum carbide or titanium carbide exposed to these conditions result in surface pores, coral-like feature growth and sub-surface helium bubbles. Reactor-relevant helium irradiation (5x1026 m-2 fluence) combined with high powered laser pulses to simulate off-normal reactor events does not significantly alter the surface morphology, as the surface nanostructures appear stable and cracks are only observed on a localized region of one sample. However, specimens show the development of an impurity layer on the surface, likely impurity deposition from the sample holder during irradiation, resulting in a mixed material layer on the surface. Helium bubbles exist in this impurity layer, and obscure conclusions about helium interactions with the carbide dispersoids. Nonetheless, it is clear that the dispersoid microstructure limits He bubble formation and subsequent surface nanostructuring, attributed to the dispersoid composition.



中文翻译:

弥散强化钨合金的高通量氦气辐照及重金属杂质层沉积的影响

钨已被选作国际热核实验堆(ITER)偏滤器区域的面向等离子体的材料(PFM),并且还被选作未来等离子体燃烧核聚变反应堆的候选PFM。在聚变设备运行期间,PFM将在高温下暴露于低能He辐射下,从而导致亚表面气泡和表面形态变化,例如孔和绒毛。碳化物弥散强化的W材料可以增强W的延展性,但在高通量He辐射下其行为仍不清楚。在这项工作中,研究了弥散强化钨材料对高温下高通量,低能He辐射的响应。钨与1、5或10 wt。暴露在这些条件下的%碳化钽或碳化钛会导致表面孔洞,珊瑚状特征的生长和表面下的氦气气泡。(26 m -2能量密度)结合高功率激光脉冲来模拟异常反应堆事件不会显着改变表面形态,因为表面纳米结构看起来稳定并且仅在一个样品的局部区域观察到裂纹。但是,样品显示在表面上形成了杂质层,在辐照期间可能会从样品架上沉积出杂质,从而在表面上形成混合材料层。氦气泡存在于该杂质层中,关于氦与碳化物弥散体相互作用的结论不清楚。尽管如此,很明显,由于分散体的组成,分散体的微观结构限制了He气泡的形成和随后的表面纳米结构。

更新日期:2020-12-14
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