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In-Pile Thermal Conductivity Measurement Method for Nuclear Fuels

机译:核燃料的桩热导电测量方法

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Thermophysical properties of advanced nuclear fuels and materials during irradiation must be known prior to their use in existing, advanced, or next generation reactors. Thermal conductivity is one of the most important properties for predicting fuel and material performance. A joint Utah State University (USU)/Idaho National Laboratory (INL) project, which is being conducted with assistance from the Institute for Energy Technology at the Norway Halden Reactor Project, is investigating in-pile fuel thermal conductivity measurement methods. This paper focuses on one of these methods - a multiple thermocouple method. This two-thermocouple method uses a surrogate fuel rod with Joule heating to simulate volumetric heat generation to gain insights about in-pile detection of thermal conductivity. Preliminary results indicated that this method can measure thermal conductivity over a specific temperature range. This paper reports the thermal conductivity values obtained by this technique and compares these values with thermal property data obtained from standard thermal property measurement techniques available at INL's High Test Temperature Laboratory. Experimental results and material properties data are also compared to finite element analysis results.
机译:在现有,先进或下一代反应器中使用之前,必须知道先进的核燃料和材料的热物理性质。导热率是用于预测燃料和材料性能的最重要性质之一。犹他州州立大学(USU)/爱达荷州国家实验室(INL)项目正在挪威Halden反应堆项目能源技术研究所的援助进行,正在研究桩基燃料导热测量方法。本文重点介绍了其中一种方法 - 一种多个热电偶方法。这种双热电偶方法采用焦耳加热的替代燃料棒来模拟体积发热,以获得对热导率的堆积检测的洞察力。初步结果表明该方法可以在特定温度范围内测量导热率。本文报道了通过该技术获得的导热率值,并将这些值与在INL的高测试温度实验室可用的标准热性测量技术中获得的热性质数据进行比较。实验结果和材料特性数据也与有限元分析结果进行比较。

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