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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >TiN-based coatings on fuel cladding tubes for advanced nuclear reactors
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TiN-based coatings on fuel cladding tubes for advanced nuclear reactors

机译:先进核反应堆燃料包壳管上的TiN基涂层

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摘要

Titanium nitride (TiN) thin films are coated on HT-9 and MA957 fuel cladding tubes and bars to explore their mechanical strength, thermal stability, diffusion barrier properties, and thermal conductivity properties. The ultimate goal is to implement TiN as an effective diffusion barrier to prevent the inter-diffusion between the nuclear fuel and the cladding material, and thus lead to a longer lifetime of the cladding tubes. Mechanical tests including hardness and scratch tests for the samples before and after thermal cycle tests show that the films have a high hardness of 28 GPa and excellent adhesion properties despite the thermal treatment. Thermal conductivity measurements demonstrate that the thin TiN films have very minimal impact on the overall thermal conductivity of the MA957 and HT-9 substrates, i.e., the thermal conductivity of the uncoated HT-9 and MA957 substrates was 26.25 and 28.44 W m ~(-1) K ~)-1), and that of the coated ones was 26.21 and 28.38 W m ~(-1) K ~(-1), respectively. A preliminary Ce diffusion test on the couple of Ce/TiN/HT-9 suggests that TiN has excellent material compatibility and good diffusion barrier properties.
机译:将氮化钛(TiN)薄膜涂覆在HT-9和MA957燃料包层管和棒上,以研究其机械强度,热稳定性,扩散阻隔性能和导热性能。最终目标是将TiN用作有效的扩散屏障,以防止核燃料与包层材料之间的相互扩散,从而延长包层管的使用寿命。在热循环测试之前和之后对样品进行的机械测试(包括硬度和划痕测试)表明,尽管进行了热处理,该膜仍具有28 GPa的高硬度和出色的粘合性能。热导率测量表明,TiN薄膜对MA957和HT-9衬底的整体热导率的影响非常小,即未涂覆的HT-9和MA957衬底的热导率分别为26.25和28.44 W m〜(- 1)K〜)-1),被覆膜的分别为26.21和28.38 W m〜(-1)K〜(-1)。对Ce / TiN / HT-9夫妇进行的初步Ce扩散测试表明,TiN具有出色的材料相容性和良好的扩散阻挡性能。

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