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首页> 外文期刊>Materials Science and Engineering >Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission
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Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission

机译：结合数字图像相关和声发射揭示铬包覆锆基燃料包壳的损伤机理

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摘要

Coated nuclear fuel claddings offer a promising, near-term solution to address the demand for next-generation, accident-tolerant fuel systems. It is expected that they will possess superior mechanical properties and greater oxidation resistance compared to current cladding technology, allowing for improved performance during beyond design-basis accident conditions. Here, we present a methodology to determine the failure mechanisms of chromium-coated zirconium-alloy claddings under expected, critical loading conditions. Three-dimensional digital image correlation and acoustic emission techniques were used in situ to monitor spatial strain and crack development of the claddings under two key, de-coupled loading conditions: expanding plug and four-point bending. Critical strain levels, at which cracking initiated, were determined to be 0.4% ε_(hoop) and 0.4% ε_(xx) for expanding plug and four-point bending, respectively. A two-dimensional fracture model was also developed for the expanding plug loading condition based on inputs determined from mechanical testing. It was concluded that coating fracture of expanding plug specimens was axisymmetric across the specimen circumference and occurred rapidly through the thickness of the chromium coating. Subsequent high temperature steam oxidation experiments on tested (cracked) expanding plug specimens showed no signs of oxidation degradation to the underlying zirconium alloy, thereby showcasing the effectiveness of the chromium coating. This comprehensive, multi-scale study is intended to inform future testing of next-generation, coated claddings and identify the resulting failure mechanisms that arise in beyond design basis accident conditions.
机译：带涂层的核燃料包壳提供了一种有前途的近期解决方案，可以满足对下一代，耐事故的燃料系统的需求。预计与目前的熔覆技术相比，它们将具有卓越的机械性能和更大的抗氧化性，从而可以在超出设计基准的事故情况下提高性能。在这里，我们提出一种方法来确定在预期的关键载荷条件下镀铬的锆合金熔覆层的失效机理。三维数字图像关联和声发射技术被用于在两个关键的，不耦合的载荷条件下（扩展插塞和四点弯曲）监测包壳的空间应变和裂纹发展。裂纹扩展开始时的临界应变水平分别确定为0.4％ε_（箍）和0.4％ε_（xx），用于扩展塞子和四点弯曲。基于机械测试确定的输入，还针对扩展的塞子加载条件开发了二维断裂模型。结论是，膨胀塞样品的涂层断裂在整个样品圆周上是轴对称的，并且在铬涂层的整个厚度上迅速发生。随后在测试的（破裂的）膨胀塞样品上进行的高温蒸汽氧化实验表明，没有氧化降解为下层锆合金的迹象，从而证明了铬涂层的有效性。这项全面的，多规模的研究旨在为下一代涂层镀层的未来测试提供信息，并确定在超出设计基准的事故情况下出现的最终故障机理。

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