Study on Nuclear Island Modeling and Parameter Measurement of Medium Pressure in Power Grid Stability Calculation

Y. Da-hai, Yuan Xiu-yue, Nian Ming, Su Yi, Tao Xiang-Yu, Xu Zhen-hua, Huo Chengxiang
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Abstract

Due to the increase of the proportion of nuclear power unit capacity in the power grid, the simulation analysis of the PWR nuclear power unit is increasingly important for power grid stability analysis, which is regarded as one of the important parts of China’s nuclear power unit. The original mathematical model of the PWR nuclear power unit is very complex and not suitable for the stable calculation and actual measurement modeling of the power grid. Based on the actual modeling of conventional islands, a simplified simulation model of the nuclear island is proposed in this paper and is conducted the actual modeling test of nuclear islands and conventional islands at the NINGDE Nuclear Power Station and FUQING Nuclear Power Station in Fujian Province. In the load test, the models and parameters of the nuclear reactor control system, temperature control circuit, steam generator, speed control system, actuator, and steam turbine were measured. The nuclear island uses the mathematical model built by MATLAB in conjunction with PSD-BPA software for simulation verification. The simulation results can truly reflect the dynamic characteristics of the nuclear islands and conventional islands of PWR nuclear power units, providing mathematical models and parameters for grid stability calculations, which can be used for dispatching safety and stability calculations.
电网稳定计算中压核岛建模及参数测量研究
随着核电机组容量在电网中所占比重的不断提高,压水堆核电机组的仿真分析对于电网稳定性分析的重要性日益凸显,电网被视为中国核电机组的重要组成部分之一。压水堆核电机组原有的数学模型非常复杂,不适合电网的稳定计算和实测建模。在常规岛实际建模的基础上,提出了简化的核岛仿真模型,并在福建省宁德核电站和福清核电站进行了核岛和常规岛的实际建模试验。在负荷试验中,对核反应堆控制系统、温控回路、蒸汽发生器、调速系统、执行机构、汽轮机等部件的模型和参数进行了测量。核岛采用MATLAB建立数学模型,结合PSD-BPA软件进行仿真验证。仿真结果真实反映了压水堆核电机组核岛和常规岛的动态特性,为电网稳定性计算提供了数学模型和参数,可用于调度安全稳定计算。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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