首页> 外文期刊>Nuclear Technology >BENCHMARK OF COMPUTATIONAL FLUID DYNAMICS SIMULATIONS USING TEMPERATURES MEASURED WITHIN ENCLOSED VERTICAL AND HORIZONTAL ARRAYS OF HEATED RODS
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BENCHMARK OF COMPUTATIONAL FLUID DYNAMICS SIMULATIONS USING TEMPERATURES MEASURED WITHIN ENCLOSED VERTICAL AND HORIZONTAL ARRAYS OF HEATED RODS

机译:使用封闭的垂直和水平方向的加热棒测量温度的计算流体动力学模拟基准

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Experiments and computational fluid dynamics/ radiation heat transfer simulations of an 8 × 8 array of heated rods within an air-filled aluminum enclosure are performed. This configuration represents a region inside the channel of a boiling water reactor fuel assembly between two consecutive spacer plates. The rods are oriented horizontally or vertically to represent transport or storage conditions. The measured and simulated rod temperatures are compared for three different rod heat generation rates to assess the accuracy of the simulation technique. Simulations show that temperature gradients in the air are much steeper near the enclosure walls than they are near the center of the rod array. The measured temperatures of rods at symmetric locations are not identical, and the difference is larger for rods close to the wall than for those far from it. Small but uncontrolledrndeviations of the rod positions away from the design locations may cause these differences. The simulations reproduce the measured temperature profiles. For a total rod heat generation rate of 300 W, the maximum rod-to-enclosure temperature difference is 150℃. Linear regression shows that the simulations slightly but systematically overpredict the hotter rod temperatures but underpredict the cooler ones. For all rod locations, heat generation rates, and rod orientations, 95% of the simulated temperatures are within 11℃ of the correlation values. For the hottest rods, which reside in the center of the domain where the air temperature gradients are small, 95% of the simulated temperatures are within 4.3℃ of the correlation values. These results can be used to assess the accuracy of using simulations to design spent nuclear fuel transport and storage systems.
机译:在充满空气的铝制外壳内,对加热棒的8×8阵列进行了实验和计算流体动力学/辐射传热模拟。该构造表示两个连续的隔板之间的沸水反应堆燃料组件的通道内部的区域。杆水平或垂直定向以代表运输或储存条件。比较了三种不同棒热产生速率下测得的和模拟的棒温度,以评估模拟技术的准确性。仿真表明,空气温度梯度在外壳壁附近比在杆阵列中心附近要陡得多。在对称位置处测得的棒的温度并不相同,并且靠近壁的棒的温度差异要远于远离壁的棒的温度差异。杆位置偏离设计位置的微小但不受控制的偏差可能会导致这些差异。模拟再现了测得的温度曲线。当棒的总发热量为300 W时,棒与外壳之间的最大温差为150℃。线性回归表明,模拟稍微但系统地高估了较热的焊条温度,但低估了较冷的焊条温度。对于所有棒位置,发热率和棒方向,95%的模拟温度在相关值的11℃以内。对于最热的棒材,它们位于空气温度梯度较小的区域的中心,其模拟温度的95%在相关值的4.3℃以内。这些结果可用于评估使用模拟设计乏核燃料运输和存储系统的准确性。

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