Study on Load-following Operation Mode of Small Sodium-Cooled Fast Reactor Nuclear Power System
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摘要: 基于RELAP/GSE联合MATLAB/Simulink平台，针对小型钠冷快堆耦合斯特林热电转换模块的方案开展仿真建模，以研究某小型钠冷快堆核电源系统的负荷跟踪运行能力及运行模式。针对负荷阶跃且无控制系统介入的极端情况，分层次考验核电源各回路系统的负荷跟踪能力，同时提出适应负荷跟踪模式下的控制方案并进行验证。仿真结果表明，该电源系统可承受±10%的负荷阶跃变化，具有较强的配合电网调峰的负荷跟踪能力。同时，本研究提出了该电源系统负荷跟踪运行模式的两套协调控制方案，通过仿真分析和比选给出了适用于小型钠冷快堆电源负荷跟踪运行模式的协调控制方案。Abstract: Based on the platform of RELAP/GSE combined with MATLAB/Simulink, a simulation model is established for the scheme of coupling Stirling thermoelectric conversion module in small sodium-cooled fast reactors, so as to study the load following operation capability and operation mode of the nuclear power supply system of a small sodium-cooled fast reactor. In the extreme case of load step and no control system intervention, the load-following capability of each loop system of nuclear power supply is tested in a hierarchical manner, and a control scheme suitable for load-following mode is proposed and verified. The simulation results show that the power supply system has the ability to withstand ±10% load step changes and has strong load-following capability to cooperate with grid peak shaving. At the same time, this research proposes two coordinated control schemes for the load-following operation mode of the power supply system, and provides a coordinated control scheme suitable for the load-following operation mode of the small sodium reactor power supply through simulation analysis and comparison.
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Key words:
- Small sodium-cooled fast reactor /
- Stirling engine /
- Load-following /
- Control scheme /
- Simulink
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图 1 小钠堆电源各模型整体耦合关系
IHX—中间热交换器
Figure 1. Overall Coupling Relationship of Each Model for Small Sodium-Cooled Fast Reactor Power Supply
图 2 负荷阶跃下降时小钠堆电源关键参数的响应
Figure 2. Response of Key Parameters of Small Sodium-cooled Reactor Power Supply under Load Step Decrease
图 3 协调控制方案一示意图
n—核功率；F—一、二回路或循环水冷却系统的工质流量；TH—斯特林发电机热壁温度；P—斯特林发电机工质压力
Figure 3. Schematic Diagram of Coordinated Control Scheme #1
图 4 负荷阶跃下降10%Pn工况下协调控制方案一仿真结果
Figure 4. Simulation Results of Coordinated Control Scheme #1 with Load Step Decrease by 10%Pn
图 5 协调控制方案二示意图
E—斯特林发电机的输出电功率
Figure 5. Schematic Diagram of Coordinated Control Scheme #2
图 6 负荷阶跃下降10%Pn工况下协调控制方案二仿真结果
Figure 6. Simulation Results of Coordinated Control Scheme #2 with Load Step Decrease by 10%Pn
表 1 小钠堆电源重要参数及其限值
Table 1. Important Parameters and Limits of Small Sodium-Cooled Fast Reactor Power Supply
参数名称 限值 堆芯出口钠温 上升不超过30℃ IHX二次侧出口钠温 上升不超过30℃ 核功率 <113%Pn Pn—额定功率 
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