针对核电二回路系统与常规火电机组热力系统在参数设定、热力特性等诸多方面的差异，本文基于ASME PTC-6等相关标准要求，以某AP1000压水堆核电机组为研究对象，首先对该机组二回路热力系统热耗保证工况（turbine heatacceptance,THA）下的表征算法进行研究，其次对不同设计工况下的特性参数进行计算，并在此基础上建立了核电机组二回路系统热力性能评估分析模型。随后应用该模型对案例机组在某一实际运行工况下的热力特性进行详细计算，在该运行工况下，低压缸第八级段、第九级段特征通流面积（CFA）较设计值偏差大，分别为6.38%和17.07%，其余级段偏差均在合理范围内，由此可初步判定第八级段、第九级段发生故障。

The steam turbine in nuclear and coal-fired power plant has many differences in parameters setting,thermal characteristics and so on.For these differences,this paper took a typical AP1000 PWR nuclear power unit as the research object and investigated the characterization algorithm of thermodynamic system of the secondary circuit in benchmark condition based on ASME PTC-6 and related standards.Then the characteristic parameters under different design conditions were calculated,and the thermal performance analysis model was established.The operation condition of the steam turbine unit could be evaluated according to the calculation results.At the same time,the module could also provide theoretical foundation and basis for the calculation under varying conditions and operation monitoring of the subsequent unit.In that operating condition,the CFA of the eighth and ninth sections in LP cylinder deviates greatly from the design value,6.38% and 17.07%,respectively,indicating the failure.Other stages are within reasonable limits.

TM623

北京节能与电力技术开发基金