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MIXING CONDITIONS IN THE LOWER PLENUM AND CORE INLET OF A BWR

机译:混合条件在BWR的下层和核心入口处

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A thermal mixing analysis of the Downcomer, Main Recirculation Pumps (MRPs) and Lower plenum of Forsmark's Unit 3 has been carried out with three separate CFD models. Several difficulties with the boundary conditions have been encountered, particularly with the MRP model. The results obtained predict stable temperature differences of around 8 K at the core inlet. Such large temperature differences have never been observed at Forsmark NPP. Temperature measurements at four positions above the Reactor Pressure Vessel (RPV) bottom give the mean value used as the core inlet temperature for core analyses with codes such as POLCA. The temperature transmitters used are rather slow and inaccurate. Still, they should be able to detect large stable temperature differences such as those predicted by the aforementioned computations. Indirect indication of the incongruity of these predictions is the possibility of fuel damage caused by such large temperature differences. Fuel damage other than the one caused by debris fretting (thread-like particles) through mechanical influence has not been reported at Forsmark NPP since the implementation of liner cladding in fuel design. Also, the aforementioned difficulties with the connection of the models throw some doubt upon the accuracy of these predictions. A completely connected model of the same RPV volume covered by the separate models predicts temperature differences at core inlet that are almost a fourth of those mentioned above, i. e. approximately 2.5 K. Most of the mixing occur downstream of the MRP diffusers, at the Lower Plenum "inlet". The reason for this prediction divergence is an impossibility of a correct transfer of complete three-dimensional flow field properties by means of boundary conditions defined at a two-dimensional inlet section.
机译:采用三种单独的CFD模型进行了脱模者,主要再循环泵(MRPS)和低压通风机的热混合分析。已经遇到了几种边界条件的困难,特别是MRP模型。得到的结果预测核心入口稳定的温度差约为8 k。在Forsmark NPP中从未观察过这种大的温度差异。在反应器压力容器(RPV)底部以上的四个位置的温度测量使用作核心入口温度的平均值,用于核心分析与POLCA等代码。使用的温度变送器相当慢且不准确。尽管如此,它们应该能够检测到诸如由上述计算预测的大的稳定温度差异。这些预测的不协调的间接指示是由这种大温差引起的燃料损坏的可能性。由于在Forsmark NPP中,在Forsmark NPP中,在燃料设计中的衬垫包层的实施以来,尚未报告通过机械影响而引起的燃料损坏。此外,模型连接的上述困难对这些预测的准确性引起了一些疑问。单独模型覆盖的相同RPV体积的完全连接的模型预测了几乎在上述核心入口处的温度差异,即i。 e。大部分2.5 K.大部分混合在下部增压室“入口”下发生MRP扩散器下游。这种预测发散的原因是通过在二维入口部分处定义的边界条件来正确地传递完整的三维流场特性。

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