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首页> 外文会议>ASME(American Society of Mechanical Engineers) Pressure Vessels and Piping Conference 2006 vol.5: High-Pressure Technology... >2D NATURAL CONVECTION AND RADIATION HEAT TRANSFER SIMULATIONS OF A PWR FUEL ASSEMBLY WITHIN A CONSTANT TEMPERATURE SUPPORT STRUCTURE
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2D NATURAL CONVECTION AND RADIATION HEAT TRANSFER SIMULATIONS OF A PWR FUEL ASSEMBLY WITHIN A CONSTANT TEMPERATURE SUPPORT STRUCTURE

机译：恒定温度支持结构下压水堆燃料组件的二维自然对流和辐射传热模拟

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摘要

Two-dimensional simulations of steady natural convection and radiation heat transfer for a 14×14 pressurized water reactor (PWR) spent nuclear fuel assembly within a square basket tube of a typical transport package were conducted using a commercial computational fluid dynamics package. The assembly is composed of 176 heat generating fuel rods and 5 larger guide tubes. The maximum cladding temperature was determined for a range of assembly heat generation rates and uniform basket wall temperatures, with both helium and nitrogen backfill gases. The results are compared with those from earlier simulations of a 7×7 boiling water reactor (BWR). Natural convection/radiation simulations exhibited measurably lower cladding temperatures only when nitrogen is the backfill gas and the wall temperature is below 100℃. The reduction in temperature is larger for the PWR assembly than it was for the BWR. For nitrogen backfill, a ten percent increase in the cladding emissivity (whose value is not well characterized) causes a 4.7% reduction in the maximum cladding to wall temperature difference in the PWR, compared to 4.3% in the BWR at a basket wall temperature of 400℃. Helium backfill exhibits reductions of 2.8% and 3.1% for PWR and BWR respectively. Simulations were performed in which each guide tube was replaced with four heat generating fuel rods, to give a homogeneous array. They show that the maximum cladding to wall temperature difference versus total heat generation within the assembly is not sensitive to this geometric variation.
机译：使用商业计算流体动力学软件包，对典型运输包装的方篮管内的14×14压水堆（PWR）乏核燃料组件的稳态自然对流和辐射传热进行了二维模拟。该组件由176个发热燃料棒和5个较大的导管组成。最高的包层温度是在一定范围内的组件发热速率和均匀的篮壁温度下确定的，同时使用氦气和氮气回填气体。将结果与7×7沸水反应堆（BWR）的早期模拟结果进行了比较。仅当氮气为回填气体且壁温低于100℃时，自然对流/辐射模拟才显示出较低的包层温度。 PWR组件的温度降低幅度大于BWR的温度降低幅度。对于氮气回填，覆层发射率（其值无法很好地表征）提高百分之十会导致PWR中最大覆层与壁温差降低4.7％，而在篮筐壁温为20％时BWR则为4.3％。 400℃。氦气回填的压水堆和压水堆分别减少了2.8％和3.1％。进行了仿真，其中每个导管都被四个发热的燃料棒所取代，以得到均匀的阵列。他们表明，组件中最大的包层与壁温之差与总热量的生成对这种几何变化不敏感。

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