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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Oxidation of aluminum alloy cladding for research and test reactor fuel
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Oxidation of aluminum alloy cladding for research and test reactor fuel

机译:用于研究和测试反应堆燃料的铝合金覆层的氧化

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The oxide thicknesses on aluminum alloy cladding were measured for the test plates from irradiation tests RERTR-6 and 7A in the ATR (advanced test reactor). The measured thicknesses were substantially lower than those of test plates with similar power from other reactors available in the literature. The main reason is believed to be due to the lower pH (pH 5.1-5.3) of the primary coolant water in the ATR than in the other reactors (pH 5.9-6.5) for which we have data. An empirical model for oxide film thickness predictions on aluminum alloy used as fuel cladding in the test reactors was developed as a function of irradiation time, temperature, surface heat flux, pH, and coolant flow rate. The applicable ranges of pH and coolant flow rates cover most research and test reactors. The predictions by the new model are in good agreement with the in-pile test data available in the literature as well as with the RERTR test data measured in the ATR. (C) 2008 Elsevier B.V. All rights reserved.
机译:在ATR(先进的测试反应器)中,通过辐射测试RERTR-6和7A测量了测试板的铝合金覆层上的氧化物厚度。所测得的厚度大大低于具有来自文献中其他反应器的类似功率的测试板的厚度。据信主要原因是由于ATR中主要冷却剂水的pH值(pH 5.1-5.3)低于我们已有数据的其他反应器(pH 5.9-6.5)。根据辐照时间,温度,表面热通量,pH值和冷却剂流速,开发了用于测试堆中用作燃料包壳的铝合金的氧化膜厚度预测的经验模型。 pH和冷却剂流速的适用范围涵盖了大多数研究和测试反应堆。新模型的预测与文献中提供的桩内测试数据以及ATR中测得的RERTR测试数据非常吻合。 (C)2008 Elsevier B.V.保留所有权利。

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