Synergistic tellurium–caesium embrittlement of Type 316 stainless steel
Synergistic tellurium–caesium embrittlement of Type 316 stainless steel
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DOI：
10.1038/295049a0
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发表时间：
1982
期刊：
影响因子：
64.8
通讯作者：
M. Adamson;E. A. Aitken;S. Vaidyanathan
中科院分区：
文献类型：
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作者：
M. Adamson;E. A. Aitken;S. Vaidyanathan
奥氏体不锈钢已成为重要的高温结构和安全壳合金，应用范围从工业过程到能源生产和转换。特别是AISI Type-300系列铁基奥氏体不锈钢，被广泛用作分别在高达700 ° C和1，000 °C的温度下运行的核燃料和化石燃料的屏障或主要安全壳材料。因此，任何观察到的化学环境对合金机械性能的有害影响，如液态锌对奥氏体不锈钢的“热”脆化1，2是非常重要的，事实上，Old 3已经提到，裂变产物，如铯，镉和碲可能在某些条件下脆化快堆燃料棒的奥氏体不锈钢包壳。在模拟反应堆内条件的化学环境中，对铁基奥氏体不锈钢的高温机械行为进行的少数研究尚未明确确定任何特别严重的化学机械降解，例如伴随应力腐蚀开裂或液态金属脆化。我们现在报告在500-700°C温度范围内，液态碲铯混合物对AISI 316不锈钢的快速、严重脆化的观察结果。我们的研究结果是使用一种测试技术，包括径向变形的小环形试样内的环境室压缩载荷在一个统一的位移速率。这种环形压缩试验技术具有易于控制化学环境和易于适应辐照材料工作的优点。
Austenitic stainless steels have become important high-temperature structural and containment alloys in applications ranging from industrial processes to energy generation and conversion. The AISI Type-300 series of iron–base austenitic stainless steels, in particular, is widely used as a barrier or primary containment material for both nuclear and fossil fuels operation at temperatures as high as 700 and 1,000 °C, respectively. Thus any observed deleterious effect of chemical environment on the alloy mechanical properties such as the ‘hot’ embrittlement of austenitic stainless steel by liquid zinc1,2is very important and, indeed, Old3has mentioned that fission products such as caesium, cadmium and tellurium might embrittle the austenitic stainless steel cladding of fast reactor fuel pins in certain conditions. The few investigations of the high temperature mechanical behaviour of iron–base austenitic stainless steels in chemical environments intended to simulate in-reactor conditions have not positively identified any particularly severe chemomechanical degradation, such as that accompanying stress corrosion cracking or liquid metal embrittlement. We now report the observation of rapid, severe embrittlement of AISI 316 stainless steel by liquid tellurium–caesium mixtures in the temperature region 500–700°C. Our results were obtained using a test technique that involves radially deforming small ring specimens contained inside an environmental chamber by compressive loading at a uniform displacement rate. This ring compression test technique has the advantages of facile control of the chemical environment and ease of adaptation for work with irradiated materials.