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首页> 外文期刊>Nuclear fusion >Effects of in situ dual ion beam (He~+ and D~+) irradiation with simultaneous pulsed heat loading on surface morphology evolution of tungsten-tantalum alloys
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Effects of in situ dual ion beam (He~+ and D~+) irradiation with simultaneous pulsed heat loading on surface morphology evolution of tungsten-tantalum alloys

机译：原位双离子束（He〜+和D〜+）辐照同时脉冲热负荷对钨钽合金表面形貌演变的影响

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摘要

The strong thermal and mechanical properties of tungsten (W) are well suited for the harsh fusion environment. However, increasing interest in using tungsten as plasma-facing components (PFCs) has revealed several key issues. These potential roadblocks necessitate more investigation of W and other alternative W based materials exposed to realistic fusion conditions. In this work, W and tungsten-tantalum (W-Ta) alloys were exposed to single (He~+) and dual (He~+ + D~+) ion irradiations with simultaneous pulsed heat loading to elucidate PFCs response under more realistic conditions. Laser only exposer revealed significantly more damage in W-Ta samples as compared to pure W samples. This was due to the difference in the mechanical properties of the two different materials. Further erosion studies were conducted to evaluate the material degradation due to transient heat loading in both the presence and absence of He~+ and/or D~+ ions. We concluded that erosion of PFC materials was significantly enhanced due to the presence of ion irradiation. This is important as it demonstrates that there are key synergistic effects resulting from more realistic fusion loading conditions that need to be considered when evaluating the response of plasma facing materials.
机译：钨（W）的强热和机械性能非常适合苛刻的熔融环境。但是，人们越来越关注使用钨作为面向等离子体的部件（PFC），这揭示了几个关键问题。这些潜在的障碍需要对暴露于现实融合条件下的W和其他W替代材料进行更多研究。在这项工作中，钨和钨钽（W-Ta）合金暴露于单（He〜+）和双（He〜+ + D〜+）离子辐照下，同时具有脉冲热负荷，以阐明更现实条件下的PFC响应。与纯W样品相比，仅激光曝光器在W-Ta样品中显示出明显更多的损坏。这是由于两种不同材料的机械性能不同所致。进行了进一步的腐蚀研究，以评估在有和没有He〜+和/或D〜+离子的情况下由于瞬态热负荷而导致的材料降解。我们得出的结论是，由于存在离子辐照，PFC材料的腐蚀显着增强。这很重要，因为它表明，在评估面向等离子体的材料的响应时，由于需要考虑更现实的融合负载条件而产生关键的协同效应。

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  • 来源
    《Nuclear fusion》 |2018年第2期|026016.1-026016.14|共14页
  • 作者

    S. Gonderman; J.K. Tripathi; G. Sinclair; T.J. Novakowski; T. Sizyuk; A. Hassanein;

  • 作者单位

    Center for materials under extreme environment (CMUXE), School of Nuclear Engineering Purdue University, West Lafayette, IN 47907, United States of America;

    Center for materials under extreme environment (CMUXE), School of Nuclear Engineering Purdue University, West Lafayette, IN 47907, United States of America;

    Center for materials under extreme environment (CMUXE), School of Nuclear Engineering Purdue University, West Lafayette, IN 47907, United States of America;

    Center for materials under extreme environment (CMUXE), School of Nuclear Engineering Purdue University, West Lafayette, IN 47907, United States of America;

    Center for materials under extreme environment (CMUXE), School of Nuclear Engineering Purdue University, West Lafayette, IN 47907, United States of America;

    Center for materials under extreme environment (CMUXE), School of Nuclear Engineering Purdue University, West Lafayette, IN 47907, United States of America;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    plasma facing materials; tungsten; tantalum; fuzz; surface morphology; ion irradiation;

    机译：等离子材料钨钽绒毛表面形态离子辐照;

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