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Experimental results on the irradiation of nuclear fusion relevant materials at the dense plasma focus 'Bora' device

机译:密集等离子体聚焦“ Bora”装置辐照核聚变相关材料的实验结果

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摘要

Samples of materials counted as perspective ones for use in the first-wall and construction elements in nuclear fusion reactors (FRs) with magnetic and inertial plasma confinement (W, Ti, Al, low-activated ferritic steel 'Eurofer' and some alloys) were irradiated in the dense plasma focus (DPF) device 'Bora' having a bank energy of ≤ 5 kJ. The device generates hot dense (T ~ 1 keV, n ~ 10l9cm~3) deuterium plasma, powerful plasma streams (v ~ 3× 10~7 cm s~(-1)) and fast (E ~ 0.1... l.0 MeV) deuterons of power flux densities q up to 10~(10) and 10~(12) Wcm~(-2) correspondingly. 'Damage factor' F = q × τ~(0.5) ensures an opportunity to simulate radiation loads (predictable for both reactors types) by the plasma/ion streams, which have the same nature and namely those parameters as expected in the FR modules. Before and after irradiation we provided investigations of our samples by means of a number of analytical techniques. Among them we used optical and scanning electron microscopy to understand character and parameters of damageability of the surface layers of the samples. Atomic force microscopy was applied to measure roughness of the surface after irradiation. These characteristics are quite important for understanding mechanisms and values of dust production in FR that may relate to tritium retention and emergency situations in FR facilities. We also applied two new techniques. For the surface we elaborated the portable x-ray diffractometer that combines x-ray single photon detection with high spectroscopic and angular resolutions. For bulk damageability investigations we applied an x-ray microCT system where x-rays were produced by a Hamamatsu microfocus source (150kV, 500 μA, 5 μm minimum focal spot size). The detector was a Hamamatsu CMOS flat panel coupled to a fibre optic plate under the GOS scintillator. The reconstruction of three-dimensional data was run with Cobra 7.4 and DIGIX CT software while VG Studio Max 2.1, and Amira 5.3 were used for segmentation and rendering. We have also provided numerical simulation of the fast ion beam action. The paper contains results on the investigations of modifications of the elemental contents, structure and properties of the materials.
机译:在具有磁和惯性等离子体约束的核聚变反应堆(FR)的第一壁和构造元件(W,Ti,Al,低活化铁素体钢“ Eurofer”和某些合金)中,被视为透视材料的材料样本为束能量≤5 kJ的密集等离子体聚焦(DPF)装置'Bora'中受到辐射。该装置可产生热致密的(T〜1 keV,n〜10l9cm〜3)氘等离子体,强大的等离子体流(v〜3×10〜7 cm s〜(-1))和快速的(E〜0.1 ... l)。 0 MeV)氘核的功率通量密度q分别高达10〜(10)和10〜(12)Wcm〜(-2)。 “损伤因子” F = q×τ〜(0.5)确保有机会通过等离子/离子流模拟辐射负荷(对于两种反应器类型都是可预测的),这些离子/离子流具有相同的性质,即那些参数与FR模块中预期的相同。辐照前后,我们通过多种分析技术对样品进行了研究。其中我们使用光学和扫描电子显微镜来了解样品表面层的损伤特性和参数。原子力显微镜用于测量辐射后的表面粗糙度。这些特性对于了解阻燃中粉尘产生的机制和价值可能非常重要,这些机理和价值可能与阻燃设施中的retention保留和紧急情况有关。我们还应用了两种新技术。对于表面,我们精心设计了便携式X射线衍射仪,该仪结合了X射线单光子检测与高光谱和角分辨率。对于批量损坏性调查,我们应用了X射线microCT系统,其中由Hamamatsu微聚焦源(150kV,500μA,5μm最小焦斑尺寸)产生了X射线。检测器是在GOS闪烁器下方耦合到光纤板上的Hamamatsu CMOS平板。三维数据的重建使用Cobra 7.4和DIGIX CT软件进行,而VG Studio Max 2.1和Amira 5.3用于分割和渲染。我们还提供了快速离子束作用的数值模拟。该文件包含有关对元素的元素含量,结构和性能进行改性研究的结果。

著录项

  • 来源
    《Nuclear fusion》 |2015年第6期|063037.1-063037.7|共7页
  • 作者单位

    The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy;

    The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy;

    The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy,Institute of Plasma Physics and Laser Microfusion, Warsaw, Poland,Institution of Russian Academy of Sciences 'A.A. Baikov Institute of Metallurgy and Material Science', Moscow, Russia;

    The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy;

    The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy;

    The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy;

    Institute of Plasma Physics and Laser Microfusion, Warsaw, Poland;

    Institution of Russian Academy of Sciences 'A.A. Baikov Institute of Metallurgy and Material Science', Moscow, Russia;

    Institution of Russian Academy of Sciences 'A.A. Baikov Institute of Metallurgy and Material Science', Moscow, Russia;

    Institution of Russian Academy of Sciences 'A.A. Baikov Institute of Metallurgy and Material Science', Moscow, Russia;

    Atomic Energy Authority, NRC, Plasma Physics and Nuclear Fusion Department, Egypt;

  • 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

    radiation tests; materials for nuclear fusion reactor; dense plasma focus 'Bora'; surface and bulk damageability;

    机译:辐射测试;核聚变反应堆材料;密集的等离子体聚焦“ Bora”;表面和整体破坏性;

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