基于时间常数的核电厂主循环泵惰转模型开发与验证

在核电厂初步设计阶段，针对反应堆进行的工况设计和安全分析均需要泵的惰转模型提供输入。现有泵的惰转模型几乎都需要已知泵的设计参数和管路系统阻力特性，但在电厂初步设计阶段，泵的详细结构设计尚未开展，管路阻力特性也难以获取。针对上述问题，提出了两种基于时间常数的主泵惰转特性曲线计算模型，并采用核电厂主循环泵的惰转试验数据进行了对比验证。分析结果表明，模型A在高转速时与试验值吻合较好，低转速时偏差较大，而模型B在整个惰转过程中与试验值均较接近，可用于核电厂的工况设计和安全分析。

Development and Verification of Coast-down Model for Coolant Pump of Nuclear Power Plant Based on Time Parameter

The coast-down model of the main pump is needed to provide input data for the reactor transient condition design and safety analysis in the preliminary design stage of a nuclear power plant. Existing pump coast down models almost need the pump design parameters and resistance characteristics of loop system, while the detailed pump structure design is not yet carried out, and resistance characteristics of pipeline are difficult to obtain in the preliminary design stage of power plant. Aiming at the above problems, two pump coast down characteristic curve calculation models based on the time parameters were proposed. In addition, the coast down models were verified by the experimental data. The analysis results show that model A agrees well with the experimental data at high speed and deviates greatly at low speed, while model B is close to the experimental data during the whole coast down process, which can be used for the condition design and safety analysis for nuclear power plant.