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首页> 外文期刊>World Journal of Nuclear Science and Technology >Thermal Hydraulic Analysis Improvement for the IEA-R1 Research Reactor and Fuel Assembly Design Modification
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Thermal Hydraulic Analysis Improvement for the IEA-R1 Research Reactor and Fuel Assembly Design Modification

机译：IEA-R1研究堆的热工水力分析改进和燃料组件设计修改

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This paper presents the sequence of activities to improve the thermal hydraulic analysis of the IEA-R1 research reactor to operate in safe conditions after power upgrade from 2 to 5 MW and core size reduction from 30 to 24 fuel assemblies. A realistic analysis needs the knowledge of the actual operation conditions (heat flow, flow rates) beyond the geometric data and the uncertainties associated with manufacturing and measures. A dummy fuel assembly was designed and constructed to measure the actual flow rate through the core fuel assemblies and its pressure drop. First results showed that the flow distribution over the core is nearly uniform. Nevertheless, the values are below than the calculated ones and the core bypass flow rate is greater than those estimated previously. Based on this, several activities were performed to identify and reduce the bypass flow, such as reduction of the flow rate through the sample irradiators, closing some unnecessary secondary holes on the matrix plate, improvement in the primary flow rate system and better fit of the core components on the matrix plate. A sub-aquatic visual system was used as an important tool to detect some bypass flow path. After these modifications, the fuel assemblies flow rate increased about 13%. Additional tests using the dummy fuel assembly were carried out to measure the internal flow distribution among the rectangular channels. The results showed that the flow rate through the outer channels is 10% - 15% lower than the internal ones. The flow rate in the channel formed between two adjacent fuel assemblies is an estimated parameter and it is difficult to measure because this is an open channel. A new thermal hydraulic analysis of the outermost plates of the fuel assemblies takes into account all this information. Then, a fuel design modification was proposed with the reduction of 50% in the uranium quantity in the outermost fuel plates. In order to avoid the oxidation of the outermost plates by high temperature, low flow rate, a reduction of 50% in the uranium density in the same ones was shown to be adequate to solve the problem.
机译：本文介绍了改善IEA-R1研究堆热水力分析的活动顺序，以将功率从2 MW提升至5 MW，并将堆芯尺寸从30减少至24个燃料组件，从而在安全条件下运行。现实的分析需要了解几何数据之外的实际操作条件（热流量，流速）以及与制造和测量相关的不确定性。设计并构造了虚拟燃料组件，以测量通过核心燃料组件的实际流量及其压降。最初的结果表明，岩心上的流量分布几乎是均匀的。尽管如此，该值仍低于计算得出的值，并且堆芯旁通流量大于先前估计的值。基于此，进行了一些活动来识别和减少旁路流量，例如降低通过样品辐照器的流量，关闭矩阵板上的一些不必要的次要孔，改善一次流量系统以及更好地适应核心组件在矩阵板上。水下视觉系统被用作检测某些旁路流路的重要工具。经过这些修改后，燃料组件的流量增加了约13％。使用虚拟燃料组件进行了其他测试，以测量矩形通道之间的内部流量分布。结果表明，通过外部通道的流速比内部通道低10％-15％。在两个相邻的燃料组件之间形成的通道中的流速是估计的参数，并且由于这是开放通道，因此难以测量。对燃料组件最外面的板进行的新的热液压分析考虑了所有这些信息。然后，提出了一种燃料设计修改方案，将最外面的燃料板中的铀量减少了50％。为了避免最外层板被高温，低流速氧化，在同一层中将铀密度降低50％足以解决该问题。

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