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Mechanical property evaluation of high burn-up nuclear fuel cladding using the ring tensile test

机译:使用环拉伸试验评估高燃尽核燃料包壳的力学性能

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摘要

In order to evaluate the degradation of the mechanical properties of Zr-based nuclear fuel cladding tubes under severe accident conditions such as a RIA (reactivity initiated accident) and LOCA (loss of coolant accident), mechanical tests that can properly simulate the degradation of these properties are needed. In the present paper, modified ring tensile tests were performed in order to evaluate the mechanical properties of high burn-up fuel cladding under a hoop loading condition in a hot cell. The tests were performed with Zircaloy-4 nuclear fuel cladding, which has a burn-up of approximately 65,000 MWd/tU in a temperature range of room temperature to 800 °C. As the first step, the hoop loading grip for the ring tensile test was designed such that a constant curvature of the specimen could be maintained during the deformation, and graphite lubricant was used to minimize the friction between the outer surface of the die insert and the inner surface of the ring specimen. The specimen for the ring tensile test was designed to limit the deformation within the gauge section and to maximize the uniformity of the strain distribution. It was confirmed that the mechanical properties under a hoop loading condition can be correctly evaluated by using this test technique. In this study, experimental results on the ductility and toughness degradation of Zircaloy-4 fuel cladding tubes under a hoop directional mechanical load simulating the RIA condition are presented.
机译:为了评估在严重事故条件下(如RIA(反应引发事故)和LOCA(冷却剂损失事故)),Zr基核燃料包壳管的机械性能下降,可以适当模拟这些劣化的机械测试属性是必需的。在本文中,进行了改进的环拉伸试验,以评估在热室中在环向加载条件下高燃耗燃料包壳的机械性能。测试使用Zircaloy-4核燃料包壳进行,该包壳在室温至800°C的温度范围内燃耗约65,000 MWd / tU。第一步,设计用于环拉伸试验的箍紧夹具,以使试样在变形过程中保持恒定的曲率,并使用石墨润滑剂来最小化模具嵌件外表面与模具之间的摩擦。环形样品的内表面。设计用于环拉伸试验的样品,以限制应变计截面内的变形并最大程度地提高应变分布的均匀性。已经证实,通过使用该测试技术,可以正确地评估在环向载荷条件下的机械性能。在这项研究中,给出了在模拟RIA条件的环向机械载荷下Zircaloy-4燃料熔覆管的延性和韧性退化的实验结果。

著录项

  • 来源
    《Metals and Materials International》 |2009年第4期|547-553|共7页
  • 作者单位

    Korea Atomic Energy Research Institute 1045 Dadeok-daero Yuseong-gu Daejeon 305-353 Korea;

    Korea Atomic Energy Research Institute 1045 Dadeok-daero Yuseong-gu Daejeon 305-353 Korea;

    Korea Atomic Energy Research Institute 1045 Dadeok-daero Yuseong-gu Daejeon 305-353 Korea;

    Korea Atomic Energy Research Institute 1045 Dadeok-daero Yuseong-gu Daejeon 305-353 Korea;

    Korea Atomic Energy Research Institute 1045 Dadeok-daero Yuseong-gu Daejeon 305-353 Korea;

    Korea Atomic Energy Research Institute 1045 Dadeok-daero Yuseong-gu Daejeon 305-353 Korea;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    high burn-up fuel cladding; ring tensile test; uniform elongation; total elongation;

    机译:高燃耗燃料包层;环拉伸试验;均匀伸长率;总伸长率;

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