首页> 外文期刊>Nuclear Technology >STUDY ON CHEMICAL INTERACTION OF U_3Si_2 DISPERSOID AND ALUMINUM MATRIX IN PLATE FUEL ELEMENTS AND ITS INFLUENCE ON THE MECHANICAL PROPERTIES
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STUDY ON CHEMICAL INTERACTION OF U_3Si_2 DISPERSOID AND ALUMINUM MATRIX IN PLATE FUEL ELEMENTS AND ITS INFLUENCE ON THE MECHANICAL PROPERTIES

机译:平板燃料中U_3Si_2分散体和铝基化学相互作用的研究及其对力学性能的影响

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摘要

Dispersion-type plate fuel elements are being fabricated with U_3Si_2 dispersoid (prepared by an innovative powder processing route) in aluminum matrix and clad in Al alloy for the modified core of the APSARA reactor by. a standard picture frame technique followed by hot roll bonding operation at the Bhabha Atomic Research Centre Metallic Fuels Division. The fabrication regime allows the fuel elements to be exposed at 500℃ for almost 5 h (total duration including hot roll bonding and blister test operation). Therefore, it is expected that during hot roll bonding and blister test operation, U_3Si_2 will chemically interact with aluminum and form an intermediate phase. Hence, the chemical interaction behavior of fuel dispersoid (U_3Si_2, prepared by powder metallurgy route) and matrix (aluminum) in plate fuel elements and its effect on mechanical properties is studied in the present paper. Therefore, a comparative study between an actual plate fuel element (i.e., U_3Si_2 dispersed in aluminum matrix and with Al alloy clad) and a sandwich plate with chemically inert material (i.e., Y_2O_3) as dispersed in aluminum matrix with Al alloy clad was carried out. The roll bonded samples were investigated through pull and peel tests, microhardness, tensile test, optical microscopy, scanning electron microscopy, electron probe microana-lysis, and X-ray diffraction for various metallurgical examinations. During the course of study, it was observed that U_3Si_2 dispersoids in actual plate fuel elements were enveloped by a different phase while the dispersoid of Y_2O_3 remained inert in the surrogate plate under a similar fabrication history. The study concludes that limited exposure of the actual fuel plate at 500℃ for 5 h results in improvement of bond strength mainly due to chemical interaction between fuel dispersoid and aluminum. The study also concludes that the tensile strength and ductility of the fuel plates did not show any adverse effects during dispersoid-matrix chemical interaction; however, the modulus of elasticity was found lower than the theoretically estimated value calculated by composite theory. The observations derived in the study are critical from the viewpoint that a decrease in the elastic modulus of the plate would adversely affect its flow-induced vibration properties during reactor operation. It may also be concluded that exposing the plate fuel elements at 500℃ for longer duration (i.e., 30 h) will result in excessive swelling because of the accelerated interaction between dispersoid and matrix, which will eventually deteriorate the desired properties.
机译:弥散型板式燃料元件是通过在铝基体中使用U_3Si_2弥散体(通过创新的粉末加工路线制备)制造的,并采用铝合金包覆以用于APSARA反应堆的改进型堆芯。 Bhabha原子研究中心金属燃料部门采用了标准的相框技术,然后进行热辊粘合操作。该制造方案允许燃料元件在500℃下暴露近5小时(包括热辊粘合和起泡测试操作在内的整个过程)。因此,可以预期的是,在热轧结合和起泡测试操作期间,U_3Si_2将与铝发生化学相互作用并形成中间相。因此,本文研究了燃料弥散体(U_3Si_2,通过粉末冶金法制备)与基体(铝)在板状燃料元件中的化学相互作用行为及其对机械性能的影响。因此,对实际的板状燃料元件(即,U_3Si_2分散在铝基体中,并包覆有铝合金)和夹有化学惰性材料(即,Y_2O_3)的三明治板分散于铝基体中,进行了比较研究。 。通过拉伸和剥离试验,显微硬度,拉伸试验,光学显微镜,扫描电子显微镜,电子探针显微分析和X射线衍射对各种冶金检验进行了研究。在研究过程中,观察到实际板状燃料元件中的U_3Si_2弥散体被不同的相包裹,而Y_2O_3的弥散体在相似的制造历史下在替代板中仍保持惰性。研究得出的结论是,实际燃料板在500℃下有限的暴露5 h会导致结合强度的提高,这主要归因于燃料弥散体与铝之间的化学相互作用。研究还得出结论,燃料板的抗张强度和延展性在弥散体-基体化学相互作用过程中没有显示出任何不利影响。然而,发现弹性模量低于通过复合理论计算的理论估计值。该研究得出的观察结果是至关重要的,因为这样的观点认为,板的弹性模量降低将不利地影响其在反应堆运行期间因流动引起的振动特性。还可以得出结论,由于分散质与基体之间的相互作用加快,将板状燃料元件在500℃下长时间(即30小时)暴露会导致过度溶胀,最终使所需的性能下降。

著录项

  • 来源
    《Nuclear Technology》 |2015年第1期|35-47|共13页
  • 作者单位

    Bhabha Atomic Research Centre, Nuclear Fuels Group, Metallic Fuels Division, Mumbai, India;

    Bhabha Atomic Research Centre, Nuclear Fuels Group, Metallic Fuels Division, Mumbai, India;

    Bhabha Atomic Research Centre, Nuclear Fuels Group, Metallic Fuels Division, Mumbai, India;

    Bhabha Atomic Research Centre, Nuclear Fuels Group, Metallic Fuels Division, Mumbai, India;

    Bhabha Atomic Research Centre, Nuclear Fuels Group, Mumbai, India;

  • 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

    plate fuel element; dispersoid; bond strength;

    机译:板状燃料元件;弥散体粘结强度;
  • 入库时间 2022-08-18 00:43:06

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