IEA-R1研究堆热工水力学分析改进及燃料组件设计改进

P. E. Umbehaun, W. M. Torres, J. Souza, M. Yamaguchi, A. T. E. Silva, R. N. Mesquita, N. Scuro, D. A. Andrade
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引用次数: 5

摘要

本文介绍了改进IEA-R1研究反应堆热工水力分析的一系列活动,以便在功率从2兆瓦升级到5兆瓦、堆芯尺寸从30个燃料组件减少到24个燃料组件后在安全条件下运行。现实的分析需要了解几何数据之外的实际操作条件(热流、流速)以及与制造和测量相关的不确定性。设计和建造了一个模拟燃料组件,以测量通过堆芯燃料组件的实际流量及其压降。第一个结果表明,堆芯上的流量分布几乎是均匀的。然而,这些值低于计算值,堆芯旁通流速大于之前估计的值。在此基础上,进行了几项活动来识别和减少旁通流量,例如降低通过样品辐照器的流速,关闭基质板上一些不必要的二次孔,改进一次流速系统,以及更好地将核心部件安装在基质板上。水下视觉系统被用作检测某些旁通流路径的重要工具。在这些修改之后,燃料组件的流速增加了约13%。使用模拟燃料组件进行了额外的测试,以测量矩形通道之间的内部流量分布。结果表明,外通道的流量比内通道低10%-15%。在两个相邻燃料组件之间形成的通道中的流速是一个估计的参数,并且由于这是一个开放通道,因此很难测量。对燃料组件最外层板的新的热工水力学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,将最外层燃料板中的铀含量减少50%。为了避免最外面的板被高温、低流速氧化,在相同的板中降低50%的铀密度足以解决这个问题。
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Thermal Hydraulic Analysis Improvement for the IEA-R1 Research Reactor and Fuel Assembly Design Modification
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.
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