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Thermodynamic and kinetic modelling of iodine induced stress corrosion cracking in nuclear fuel sheathing.

机译:核燃料护套中碘引起的应力腐蚀开裂的热力学和动力学模型。

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摘要

Iodine induced stress corrosion cracking, I-SCC, is a recognized factor in the operation of nuclear reactors requiring the implementation of mitigation measures for the new Advanced CANDU Reactor (ACR) because of a higher burn-up and different refuelling scheme employed by the reactor design. I-SCC is believed to depend on certain factors such as iodine concentration, oxide layer type and thickness on the fuel sheath, irradiation history, metallurgical parameters related to the sheath like texture and microstructure, and the mechanical properties of zirconium alloys. This work develops a mechanistic kinetic model, accounting for the iodine chemistry and thermodynamics in the fuel-to-sheath gap, with a finite-element technique describing the mechanism of I-SCC, and its implementation using the COMSOL MultiphysicsRTM commercial software platform. This study also proposes remedies for I-SCC with suggested experimentation.
机译:碘引起的应力腐蚀裂纹,I-SCC,是核反应堆运行中公认的因素,需要对新的先进坎杜反应堆(ACR)采取缓解措施,因为反应堆采用了更高的燃耗和不同的加油方案设计。据信,I-SCC取决于某些因素,例如碘浓度,燃料护套上的氧化层类型和厚度,辐照历史,与护套有关的冶金参数(如织构和微观结构)以及锆合金的机械性能。这项工作使用有限元技术描述了I-SCC的机理及其在COMSOL MultiphysicsRTM商业软件平台上的实现,从而开发了一种力学动力学模型,考虑了燃料与鞘之间的碘化学和热力学。这项研究还通过建议的实验为I-SCC提出了补救措施。

著录项

  • 作者

    Kleczek, Monika R.;

  • 作者单位

    Royal Military College of Canada (Canada).;

  • 授予单位 Royal Military College of Canada (Canada).;
  • 学科 Engineering Nuclear.
  • 学位 M.A.Sc.
  • 年度 2010
  • 页码 137 p.
  • 总页数 137
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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