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首页> 外文学位 >Monitoring the Progress of Damage in a SiCF-SiC M Composite Nuclear Fuel Cladding Under Internal Pressure Using Acoustic Emission
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Monitoring the Progress of Damage in a SiCF-SiC M Composite Nuclear Fuel Cladding Under Internal Pressure Using Acoustic Emission

机译：使用声发射监测内压下SiCF-SiC M复合核燃料包壳的破坏进程

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摘要

The relation between the progress of damage and the acoustic emission (AE) activity of a nuclear grade Sif-SiCm composite tubing under internal pressure was studied. The nuclear grade Sif-SiCm composite tubing is manufactured by the company General Atomics (GA) and made of nuclear grade HI Nicalon type S fiber preforms following a chemical vapor infiltration (CVI) technique. Sif-SiCm composites are good candidates to replace current nuclear fuel cladding materials because of the good chemical stability and strength at high temperatures. In this work, a Sif-SiCm composite tubing was tested under internal pressure at room temperature (RT) to study the damage behavior under hoop loading conditions that occur during a Loss of Coolant Accident (LOCA). In an additional effort, a Pellet Cladding Mechanical Interaction (PCMI) resulting from Reactivity Initiated Accident (RIA) conditions and a thermal shock, meant to represent a reactor reflood, were simulated. The PCMI was simulated by loading the Sif-SiCm composite tubing, at temperature of 1373 °K (1100 °C), using a solid surrogate and a heating technique that induces temperature gradients through the wall of the Sif-SiCm composite tubing. The thermal shock was simulated by quenching a Sif-SiC m composite tubing in water. In all tests, the AE technique was used to monitor the progress of damage by recording the acoustic emission activity within the material using a miniature AE sensor. Digital image correlation (DIC) was used to calculate the full-field strain distribution on the outer surface of the sample. In the case of the high temperature test, a high temperature resistant speckle patter and a light filtering technique were used. Microscopic and XCT imaging were used to analyze the damage in the samples caused by the applied load. In the case of the internal pressure loading, a method that relates the acoustic emission activity within the material and the progress of damage is proposed. Damage is the representation of the deterioration of the elastic constants when a load is applied and is typically represented by a damage variable. By finding a correlation between the AE parameters and the damage variable it is possible to predict strains/stresses under specific uniaxial loading conditions. Finally, the Continuum Damage Mechanics method was used to model the mechanical strains of the Sif-SiCm composite tubing under internal pressure and will be compared to the method proposed.
机译：研究了内压下核级Sif-SiCm复合管的损伤进程与声发射（AE）活性之间的关系。核级Sif-SiCm复合管是由General Atomics（GA）公司生产，并采用化学气相渗透（CVI）技术由核级HI Nicalon S型纤维预成型坯制成。 Sif-SiCm复合材料具有良好的化学稳定性和高温强度，是替代当前核燃料覆层材料的理想选择。在这项工作中，在室温（RT）的内部压力下对Sif-SiCm复合管进行了测试，以研究在冷却剂事故（LOCA）期间发生的环向加载条件下的破坏行为。在一项额外的工作中，模拟了反应性引发事故（RIA）条件和热冲击（意在表示反应堆再驱）的造粒覆层机械相互作用（PCMI）。通过使用固态替代物和加热技术在Sif-SiCm复合管壁上引入温度梯度，在1373°K（1100°C）的温度下加载Sif-SiCm复合管来模拟PCMI。通过在水中淬火Sif-SiC m复合管来模拟热冲击。在所有测试中，使用AE技术通过使用微型AE传感器记录材料内的声发射活动来监视损坏的进程。数字图像相关性（DIC）用于计算样品外表面的全场应变分布。在高温测试的情况下，使用了耐高温斑点图案和​​滤光技术。使用显微镜和XCT成像分析由于施加的载荷对样品造成的损坏。在内部压力载荷的情况下，提出了一种方法，该方法将材料内的声发射活动与损坏的进程联系起来。损伤是当施加载荷时弹性常数变差的表示，通常由损伤变量表示。通过找到AE参数和损伤变量之间的相关性，可以预测特定单轴载荷条件下的应变/应力。最后，采用连续损伤力学方法对Sif-SiCm复合管在内部压力下的机械应变进行建模，并将其与提出的方法进行比较。

著录项

  • 作者

    Alva, Luis H.;

  • 作者单位

    University of South Carolina.;

  • 授予单位 University of South Carolina.;
  • 学科 Mechanical engineering.
  • 学位 Ph.D.
  • 年度 2018
  • 页码 131 p.
  • 总页数 131
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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