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An assessment of silicon carbide as a cladding material for light water reactors

机译:评估碳化硅作为轻水反应堆的包层材料

摘要

An investigation into the properties and performance of a novel silicon carbide-based fuel rod cladding under PWR conditions was conducted. The novel design is a triplex, with the inner and outermost layers consisting of monolithic SiC, while the middle layer consists of a SiC fiberwound composite. The goal of this work was evaluation of the suitability of this design for use as a fuel rod cladding material in PWRs and the identification of the effects of design alternatives on the cladding performance. An in-core loop at the MITR-II was used to irradiate prototype triplex SiC cladding specimens under typical PWR temperature, pressure, and neutron flux conditions. The irradiation involved about 70 specimens, of monolithic as well as of triplex constitution, manufactured using several different processes to form the monolith, composite, and coating layers. Post-irradiation examination found some SiC specimens had acceptably low irradiation-enhanced corrosion rates and predictable swelling behavior. However, other specimens did not fare as well and showed excessive corrosion and cracking. Therefore, the performance of the SiC cladding will depend on appropriate selection of manufacturing techniques. Hoop strength testing found wide variations in tensile strength, but patterns or performance similar to the corrosion tests. The computer code FRAPCON, which is widely used for today's fuel assessment, modified properly to account for SiC properties, was applied to simulate effects of steady-state irradiation in an LWR core. The results demonstrated that utilizing SiC cladding in a 17x17 fuel assembly for existing PWRs may allow fuel to be run to somewhat higher burnup. However, due to lack of early gap closure by creep as well as the lower conductivity of the cladding, the fuel will experience higher temperatures than with zircaloy cladding. Several options were explored to reduce the fuel temperature, and it was concluded that annular fuel pellets were a solution with industrial experience that could improve the performance sufficiently to allow reaching 40% higher burnup. Management of the fuel-cladding gap was identified as essential for control of fuel temperature and PCMI. SiC cladding performance may be limited unless cladding/fuel conductivity or gap conductance is improved.
机译:在压水堆条件下,对新型碳化硅基燃料棒包壳的性能进行了研究。新颖的设计是三层结构,其内层和最外层由整体式SiC组成,而中间层由SiC纤维缠绕复合材料组成。这项工作的目的是评估这种设计在压水堆中用作燃料棒包层材料的适用性,并确定设计方案对包层性能的影响。在典型的PWR温度,压力和中子通量条件下,使用MITR-II的堆芯内环照射原型三重SiC覆层样品。辐照涉及大约70个样品,这些样品是整体的和三层结构的,使用几种不同的工艺制造而成,以形成整体,复合和涂层。辐照后检查发现某些SiC样品具有可接受的低辐照增强腐蚀速率和可预测的溶胀行为。但是,其他标本也表现不佳,并且显示出过度的腐蚀和开裂。因此,SiC覆层的性能将取决于适当选择的制造技术。箍强度测试发现抗张强度变化很大,但是图案或性能类似于腐蚀测试。计算机代码FRAPCON已被广泛用于当今的燃料评估,并经过适当修改以适应SiC的特性,并被用于模拟轻水堆堆芯中稳态辐射的影响。结果表明,对于现有的压水堆,在17x17的燃料组件中使用SiC覆层可以使燃料的燃耗更高。但是,由于缺乏早期的蠕变封闭间隙以及包层的电导率较低,因此燃料比锆合金包层的温度更高。研究了降低燃料温度的几种选择,并且得出的结论是,环形燃料芯块是一种具有工业经验的解决方案,可以充分提高性能以使燃耗提高40%。燃油包层间隙的管理被确定为控制燃油温度和PCMI的关键。除非改善覆层/燃料电导率或间隙电导率,否则SiC覆层性能可能会受到限制。

著录项

  • 作者

    Carpenter David Michael;

  • 作者单位
  • 年度 2011
  • 总页数
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类

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