基于PSASP的压水堆核电站堆芯建模及仿真研究  

Simulation of Dynamic Mathematical Modeling for PWR Nuclear Power Plant Core Based on PSASP

作　　者：施希[1] 刘涤尘[1] 吴萍[1] 赵洁[1] 熊莉[1] 张园园[1] 赵遵廉[2] 

机构地区：[1]武汉大学电气工程学院,武汉430072 [2]国家电网公司,北京100031

出　　处：《核动力工程》2009年第3期126-130,共5页Nuclear Power Engineering

摘　　要：利用PSASP软件的用户自定义模块功能搭建堆芯模型,分别对堆芯模型在反应性阶跃扰动和冷线温度阶跃扰动下的动态响应过程进行模拟仿真。仿真结果表明,堆芯由于温度效应和中毒效应而具有一定的自稳定性,与实际数据及理论分析吻合,证明该模型真实有效。Neutron dynamic model and fuel/coolant thermal output dynamic model were implemented in PSASP through a user-defined program. Based on the mathematical models of different orders, the dynamic behaviors of the NPP core under the input of step disturbance of reactivity and cool-line temperature were simulated in PSASP respectively. The simulation results demonstrate the self-stability of NPP core with temperature effect and poisoning effect, which is consistent with the real-world data. Moreover, the simulation validated the proposed core model, and it can be further used in dynamic calculation of the power system.

关 键 词：压水堆 堆芯建模 动态仿真 PSASP软件 

分 类 号：TL32[核科学技术—核技术及应用]