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首页> 外文会议>STP 1467; International Symposium on Zirconium in the Nuclear Industry; 20040613-17; Stockholm(SE) >Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications
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Improved ZIRLO™ Cladding Performance through Chemistry and Process Modifications

机译：通过化学和工艺改进提高了ZIRLO™熔覆性能

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Since the introduction of the ZIRLO™ alloy for use in commercial nuclear light water reactors (LWRs) in the early nineties, work has continued on identifying chemistry and process changes to improve further the in-reactor corrosion performance of the alloy. Relative to the reference ZIRLO chemistry of Zr-1%Nb-1%Sn-0.1%Fe, a series of Zr-xNb-ySn-zFe alloys was fabricated to strip material and autoclave tested. The goal was to identify Zr-Nb-Sn-Fe compositions that would result in lower uniform corrosion rates in pure water and steam environments, while retaining resistance to accelerated corrosion in abnormal chemistry conditions, such as elevated lithium levels. The results of the study identified a reduction in tin content as having the greatest impact on improving the uniform corrosion performance. However, a minimum tin content was required to avoid accelerated corrosion in water containing 70-ppm Li. In the processing area, an extensive study was conducted to evaluate the relationship between thermal-mechanical processing, alloy microstructure (e.g., second phase particles), and corrosion performance. Processing variables following β-phase heat treatments included cold work, annealing temperature, and annealing time. Long-term autoclave tests performed in 633°K water containing 70-ppm lithium showed the uniform corrosion rate of the alloy is essentially optimized in cold-worked material after only 1 h of anneal at temperatures higher than 823°K. The autoclave results also showed a lower corrosion rate with decreasing processing temperatures. A low tin version of the ZIRLO alloy, with approximately 0.75% tin content, was fabricated into fuel cladding and inserted as fuel rods in a commercial pressurized water reactor. After two 18-month cycles at high fuel duty and average burnups greater than 52 GWD/MTU, the peak oxide thickness in the low tin ZIRLO was significantly lower than reference ZIRLO.
机译：自从90年代初将ZIRLO™合金引入商用核轻水反应堆（LWR）中以来，就一直致力于确定化学和工艺变化以进一步改善合金的反应器内腐蚀性能。相对于Zr-1％Nb-1％Sn-0.1％Fe的参考ZIRLO化学成分，制造了一系列Zr-xNb-ySn-zFe合金以剥离材料并进行高压釜测试。目的是确定Zr-Nb-Sn-Fe组合物，这些组合物在纯水和蒸汽环境中会导致较低的均匀腐蚀速率，同时在异常化学条件（例如锂含量升高）下保持对加速腐蚀的抵抗力。研究结果表明，锡含量的降低对改善均匀腐蚀性能的影响最大。但是，需要最小锡含量以避免在含70 ppm Li的水中加速腐蚀。在加工领域，进行了广泛的研究以评估热机械加工，合金微观结构（例如第二相颗粒）和腐蚀性能之间的关系。 β相热处理后的工艺变量包括冷作，退火温度和退火时间。在含70 ppm锂的633°K水中进行的长期高压釜测试表明，在高于823°K的温度下仅退火1小时后，在冷加工材料中合金的均匀腐蚀速率基本得到优化。高压釜的结果还表明，随着加工温度的降低，腐蚀速率降低。将含锡量约为0.75％的低锡版本ZIRLO合金制成燃料包壳，并将其作为燃料棒插入商用加压水反应堆中。在高燃料负荷和平均燃耗大于52 GWD / MTU的情况下进行两个18个月的循环后，低锡ZIRLO中的峰值氧化层厚度明显低于参考ZIRLO。

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