大型核电机组冷却剂屏蔽主泵动态模型及响应特性研究

为了提高核安全性,新型压水堆核电机组冷却剂主泵采用无轴密封式屏蔽电动机泵,但其转动惯量明显小于常规轴密封泵,因此具有不同的动态响应特性。针对屏蔽主泵转动惯量较小、对电压、频率波动敏感等特性,考虑运行过程中的摩擦转矩,建立了屏蔽主泵动态模型,并将其接入核电机组系统仿真模型。比较验证了主泵动态模型的有效性,并仿真分析了主泵惰转特性和频率、电压扰动响应特性及其对堆芯功率的影响。结果表明,摩擦转矩对屏蔽主泵半流量惰转时间有较明显影响,建模时应予以考虑;频率扰动对主泵转速、流量的影响比电压扰动更明显,在运行中应提高厂用电供电质量。

基于APROS的核电系统建模与控制方法研究

随着核电系统建模日益朝着准确化、精细化方向发展,对三维堆芯与热工水力模型耦合的研究也逐渐增多,这为控制系统的设计提供了更好的模型基础。本研究采用APROS软件对VVER-1000反应堆进行了三维堆芯与热工水力耦合建模,并设计了基于模型预测控制(MPC)的负荷跟踪控制系统和其他控制系统;随后利用稳态和瞬态仿真结果对该模型进行了验证,结果表明该模型仿真效果良好;利用三维堆芯可视化的优点,进一步验证了MPC负荷跟踪控制器的性能和安全性。这一研究不仅为核电系统研究提供了模型基础,也为先进功率控制系统的安全性分析提供了实践经验。

Modeling of Operators' Workload in a Nuclear Power Plant

Accidents in a nuclear power plant are coped with by operators in the main control room (MCR). An analysis of the workload of operators in a MCR after the happening of initiating events is helpful to the alleviation of human errors and to the promotion of training efficiency. This paper establishes a framework of how man is located in a man-machine interface of a nuclear power plant (NPP) as well as a simulation of the man-machine scenario in accidents in NPPs, including the simulation of the operators' task and cognitive work and the establishment of task analysis. On the basis of the above, a model of the dynamic changes of the operators' tasks is constructed and a computation of operators' workload is conducted.