Preliminary study of lead-bismuth reactor system analysis code development
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摘要: 为解决多维计算程序对铅铋堆主回路进行长时间模拟时所需计算资源庞大的问题，基于自主开发的一维CFD程序，将零维点堆动力学模型及二维燃料棒传热模型集成到其中，并进行多物理场耦合，开发了一款适用于池式铅铋堆的系统分析程序。使用OECD/NEA发布的加速器驱动次临界系统（ADS）失束事故国际基准例题，对所开发程序进行稳态以及瞬态验证，以确保模型准确性。验证结果表明，所开发程序在关键参数上与发布结果吻合较好，且所需计算资源明显小于多维程序，证明了该程序可以对池式铅铋堆进行初步的热工水力及安全分析。Abstract: To solve the problem that multidimensional computing code needs huge computing resources when it simulates the lead-bismuth reactor for a long time, based on the self-developed one-dimensional CFD code, integrating the zero-dimensional point reactor dynamics model and the two-dimensional fuel rod heat transfer model, and carring out the multi-physical field coupling, we have developed a system safety analysis code for lead-bismuth pool reactor. The international benchmark for Accelerator Driven Sub-critical System (ADS) beams transient accident, which was published by OECD/NEA, was used to process the steady-state and transient validation, and to ensure the accuracy of the model. The verification results show that the code developed is in good agreement with the published results in terms of key parameters, and the computational resources required are obviously smaller than those of the multi-dimensional computing code. It is proved that this code can be used for preliminary thermo-hydraulic and safety analysis of lead-bismuth reactor.
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图 9 平均通道燃料中平面温度及活性区冷却剂出口温度
Figure 9. Average pin fuel temperature at fuel zone midplane and outlet coolant temperature
图 10 热通道燃料中心中平面温度及活性区冷却剂出口温度
Figure 10. Hottest pin fuel centerline temperature at fuel zone midplane and outlet coolant temperature
表 1 流量及功率分配
Table 1. Flow and power distribution
No. number of fuels normalized power traffic share 1 8316 1.0000 0.7469 2 1944 1.4375 0.1746 3 540 0.1000 0.0785 
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表 2 平均通道燃料中心及堆芯活性区冷却剂出口下降温度
Table 2. Average pin fuel center and outlet coolant drop temperature
time/s fuel centerline/K fuel centerline
error/%outlet coolant /K outlet coolant
error/%this code OECD/NEA this code OECD/NEA 1 68 70 2.9 13.2 13 1.5 3 181 180 0.5 36 35 2.8 6 286 300 4.6 61 60 1.6 12 373 370 0.8 86 85 1.2
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表 3 热通道燃料中心及堆芯活性区冷却剂出口下降温度
Table 3. Hottest pin fuel center and outlet coolant drop temperature
time/s fuel centerline/K fuel centerline
error/%outlet coolant /K outlet coolant
error/%this code OECD/NEA this code OECD/NEA 1 97 93 4.3 19 20 5.0 6 420 408 2.9 86 80 5.0
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