Study on Operation of Small Lead-Based Fast Reactor Based on Constant Ratio of Flow to Power
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摘要: 为开展小型铅基快堆运行策略研究，建立堆芯传递函数模型，利用比例-积分-微分（PID）控制器，结合控制棒驱动机构，分别设计堆芯流量功率比恒定与堆芯稳定核功率的运行方案。分别建立不同运行策略下的控制系统，开展一回路流量阶跃和堆芯反应性扰动仿真。结果表明，在引入一回路流量阶跃下降工况下，稳定核功率运行方案由于堆芯功率恒定而导致堆芯出口温度过高；在流量功率比恒定方案下，堆芯功率跟随一回路流量下降从而保证堆芯出口温度迅速稳定在安全范围内；在阶跃反应性扰动下，2种方案均可迅速调控堆芯功率的上冲幅度和超调量，堆芯出口温度基本维持恒定。Abstract: In order to study the operation strategy of small lead-based fast reactor, the core transfer function model is established, and the operation schemes of constant ratio of core flow to power and stable core nuclear power are designed by using proportional-integral-derivative (PID) controller and control rod drive mechanism. The control systems with different operation strategies are established respectively, and the simulation of primary loop flow step and core reactivity disturbance is carried out. The results show that under the condition of introducing primary loop flow step down, the stable nuclear power operation scheme leads to the high core outlet temperature due to the constant core power; in the case of constant ratio of flow to power, the core power decreases with the primary flow, so that the core outlet temperature is stable in a safe range. When there is step reactivity disturbance, both schemes can quickly control the overshoot and overshoot of core power, and the core outlet temperature is basically constant.
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图 2 稳定核功率运行方案原理
Pr—相对功率变化率
Figure 2. Principle of Stable Nuclear Power Operation Scheme
图 4 满功率下引入5%一回路流量阶跃下降的系统响应
Figure 4. System Response with 5% Primary Loop Flow Step Down at Full Power Level
图 5 满功率下引入10%一回路流量阶跃下降的系统响应
Figure 5. System Response with 10% Primary Loop Flow Step Down at Full Power Level
图 6 满功率下引入5×10−4阶跃反应性的系统响应
Figure 6. System Response with 5×10−4 Step Reactivity at Full Power Level
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