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首页> 外文期刊>World Journal of Nuclear Science and Technology >Thermal Conductivity Measurement of Zr-ZrO2 Simulated Inert Matrix Nuclear Fuel Pellet
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Thermal Conductivity Measurement of Zr-ZrO2 Simulated Inert Matrix Nuclear Fuel Pellet

机译：Zr-ZrO2模拟惰性基质核燃料颗粒的热导率测量

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摘要

For an evaluation of a thermal conductivity of Zr + 30 vol% ZrO2 simulated inert matrix nuclear fuel pellet, a simulated fuel pellet was fabricated using a hot-pressing method at 800°C in a vacuum and at a 20 MPa load. And several thermophysical properties of the simulated inert matrix fuel pellet were measured and calculated. The thermal diffusivity and linear thermal expansion as a function of temperature of the simulated fuel pellet were measured using a laser flash method and a dilatometry, respectively. Finally, based on the experimental data, the thermal conductivity of the simulated inert matrix fuel pellet was calculated and evaluated.
机译：为了评估Zr + 30 vol％ZrO2模拟惰性基质核燃料芯块的导热系数，使用热压方法在真空中，800℃和20 MPa的负载下制作了模拟燃料芯块。并对模拟的惰性基质燃料颗粒的几种热物理性质进行了测量和计算。分别使用激光闪光法和热膨胀法测量作为模拟燃料芯块温度的函数的热扩散率和线性热膨胀。最后，基于实验数据，计算并评估了模拟的惰性基质燃料颗粒的热导率。

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