摘要
蒸汽发生器水位控制的瞬态计算与分析是评估、预测核电站反应堆停堆、汽轮机停机的重要途径。目前的瞬态计算方法,大多未将控制过程纳入计算模型中,且核岛、常规岛按设计边界划分进行独立计算。本文将CPR1000核岛、常规岛瞬态控制过程进行整体分析和计算,在现有瞬态计算方法的基础上,在模型中加入了反馈控制环节,提高了计算的准确度。通过对计算结果及模型的误差进行分析,提出指导设计及运行的结论,进一步提高计算准确度的方法。
Transient calculation and analysis of steam generator water level is an important part related to reactor trip and turbine trip.For the usual transient calculation,the control process is not taken into account and it is carried out separately by nuclear island designer and conventional island designer according to the scope of design.In this paper,an optimized model is set up with control process,nuclear island and conventional island is analyzed at the same time,and calculation accuracy is improved.The conclusion and the factors related to the accuracy of this optimized model are discussed.
出处
《核科学与工程》
CSCD
北大核心
2010年第S1期155-161,共7页
Nuclear Science and Engineering
关键词
核电站
蒸汽发生器水位
瞬态计算
快速降负荷
nuclear power station
steam generator water level
transient calculation
fast power unload