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Thermal conductivity of liquid lead-bismuth alloys, possible coolants for fourth generation spallation nuclear reactors

机译:液态铅-铋合金的导热系数,第四代散裂核反应堆可能的冷却剂

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摘要

The lead-bismuth eutectic (Pb-wt1%45 Bi-wt%55) appears to be a good coolant for the fourth generation spallation nuclear reactors. We determine the thermal conductivity (lambda) of liquid Pb-Bi for large range of compositions and temperatures from the experimental values of the electrical resistivity (rho) and the thermoelectric power (S). These electronic transport properties are obtained with an automated device that combines a measurement of rho using a four-point probe technique and a measurement of S employing a small AT method. The thermal conductivity has also been determined theoretically with a numerical calculation obtained by using the Faber-Ziman formalism. (c) 2007 Elsevier B.V. All rights reserved.
机译:铅铋共晶(Pb-wt1%45 Bi-wt%55)似乎是第四代散裂核反应堆的良好冷却剂。我们从电阻率(rho)和热电功率(S)的实验值确定大范围组成和温度下液体Pb-Bi的热导率(λ)。这些电子传输特性是通过自动设备获得的,该设备将使用四点探针技术的rho测量和使用小AT方法的S测量相结合。理论上,导热率也已通过使用Faber-Ziman形式主义获得的数值计算确定。 (c)2007 Elsevier B.V.保留所有权利。

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