Study on Loading Pattern for Long-cycle Lead-cooled Fast Reactor Core
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摘要: 铅冷快堆具有系统简单、自然安全的特点，是最具发展潜力与现实性的四代核电堆型之一。由于铅冷却剂具有密度大、运行温度高、不透明等特性，导致铅冷快堆倒换料技术难度大、过程复杂且耗时，影响核电厂的经济性和安全性，因而增加循环长度、减少倒换料次数，成为大型商用铅冷快堆设计研究的重要内容。本文从工程需求出发分析了核燃料类型、燃料元件及组件形式、反射层材料、控制棒布置方式、易裂变核素再生区设置方法等因素对铅冷快堆循环长度的影响规律，建立铅冷快堆长循环堆芯装载方法，为大型商用铅冷快堆堆芯物理设计优化提供参考。Abstract: Lead-cooled fast reactor system is simple with natural safety, and it is one of the Generation Ⅳ nuclear power reactors with the most development potential and reality. Due to the high density, high operating temperature and opacity of lead coolant, the core refueling process is very difficult, complex and time-consuming, which affects the economy and safety of nuclear power plants. Therefor, increasing the core cycle length and reducing the refueling frequency have become an important aspect of the design and research of large-scale commercial lead-cooled fast reactor. Based on the engineering requirements, this paper analyzes the influence laws of the factors such as nuclear fuel type, fuel element and assembly form, reflector material, control rod layout, and the setting method of fissile nuclides blanket zone on the cycle length of lead-cooled fast reactor, and establishes the loading method of long-cycle core of lead-cooled fast reactor, which provides reference for the optimization of physical design of large commercial lead-cooled fast reactor.
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Key words:
- Lead-cooled fast reactor /
- Generation Ⅳ nuclear reactor /
- Long cycle /
- Physical design
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图 3 堆芯径向布置示意图
1—标准燃料组件；2—铅反射层组件；3—自动调节棒组；4—能动紧急停堆棒组；5—非能动紧急停堆棒组；6—燃耗补偿棒组
Figure 3. Schematic Diagram of Core Radial Configuration
表 1 铅冷快堆堆芯主要参数
Table 1. Key Parameters of the Lead-cooled Fast Reactor Core
参数名 数值或描述 热功率/MW 1500 堆芯入口温度/℃ 420 堆芯出口温度/℃ 540 系统流量/(t·s−1) 84 冷却剂流速/(m·s−1) ≤2.0 燃料元件类型 棒元件 燃料组件形式 正方形 核燃料 U-20%Pu-10%Zr 换料周期/a ≥10 
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