提高核电站汽轮机组发电能力可行性研究是响应国家号召积极 进行节能减排，同时还是立足于企业经济效益，尤其是在技术日益进 步，核电工程和核电技术大发展的时期，对已有核电机组（技术相对 落后）进行安全性和经济性改进更有其必要性。 核电站汽轮机组与常规电厂汽轮机组存在较大区别，核电站汽轮 机不仅容量较大工作在湿蒸汽区，而且二回路功率受限于一回路的最 大热功率，因此对设备的改造不仅要考虑到经济性，而且还要考虑对 电站安全性的影响。本文通过确定机组发电能力评价原则和机组发电 能力统计模型，保证了对机组出力能力评定的有效性，并建立机组出 力故障智慧树，有效的对影响机组出力能力的各项重要因素做了定性 分析。建立了核电二回路热效计算模型，并通过对机组变工况的实例 计算，验证了该模型的有效性。利用该模型重点对基准热功率测量系 统、冷凝器性能维护、重要阀门查漏等已经实施改进措施，进行了定 量分析，验证了这些改进措施的有效性。结合缸效率模型验证了高压 缸隔板改造的可行性，同时，结合汽水分离再热器模型，证明了在对 汽水分离再热器系统新蒸汽进行节流改造，可以降低低压缸进汽温 度，提高整体功率。 关键词，核电站，发电能力，热力系统，等焓降，模型，可行性第 I 页 FEASIBILITY STUDY TO INCREACE GENERATING CAPACITY FOR NUCLEAR POWER STATION ABSTRACT Feasibility studies to improve gas turbine power generation capacity of nuclear power plant are underway to respond to the call of country energy-saving emission reduction, is also based on the economic efficiency of enterprises, especially in the more and more advanced technology, nuclear power engineering and nuclear power technology of the period of great development, it needs to improve more for the existing nuclear power generating units (relatively backward technology) for more safety and economy . Nuclear power plant gas turbine and conventional gas turbine power plant there is a big difference between not only the capacity of nuclear power plant steam turbine work using wet steam, but also secondary-loop power is subject to the largest thermal power of primary-loop, so the transformation of the equipment should not only take into account the economy, but also consider the impact of power plant safety. In this paper, by identifying the assessment principle of generating capacity and model of the statistical generating capacity to ensure that the crew assessed the effectiveness of our efforts and contribute to fault intelligence unit set up the tree and effective efforts to influence the capacity of generating units of the important factors that make a qualitative analysis . Build up a nuclear power plant thermal efficiency calculation of secondary-loop model, and calculated the different variable conditions of units to verify the validity of the model. The focus of the model using the baseline measurement of thermal power system, the condenser performance maintenance, leak detection of important valves have been implemented to improve the measures to carry out a quantitative analysis, proved the correctness of these improvements. Combined with the efficiency of model-cylinder proved the feasibility of the transformation for high-pressure cylinder, at the same time, combined with separator re-heater model demonstrated that it is effective to improve the overall power, reducing the new stream pressure to reduce the stream temperature of low-pressure cylinder.第 II 页 KEYWORDS: nuclear power station, generating capacity, thermal system, enthalpy drop, model, feasibility第 I 页 目录 摘要........................................................................................................................................................I ABSTRACT ............................................................................................................................................ I 目录..........................................................................................................................................................I 符号与标记...........................................................................................................................................III 第一章 绪论..........................................................................................................................................1 1.1 背景概述 .......................................................................................................................................... I 1.2 国内外现状分析 ..............................................................................................................................1 1.3 课题研究的工程需求和现实意义...................................................................................................2 1.4 本章小结...........................................................................................................................................3 第二章 核电汽轮机组特点....................................................................................................................5 2.1 系统与设备特点...............................................................................................................................6 2.2 参数与运行特点 ..............................................................................................................................7 2.3 大亚湾和岭澳核电站汽轮机主要参数...........................................................................................8 2.4 本章小结 ........................................................................................................................................10 第三章 核电汽轮机热效模型..............................................................................................................11 3.1 核电汽轮机组热力系统简化.........................................................................................................11 3.2 核电汽轮机热力平衡模型.............................................................................................................13 3.3 本章小结.........................................................................................................................................14 第四章 核电机组发电能力分析..........................................................................................................16 4.1 核电汽轮机组发电能力评价原则.................................................................................................16 4.2 发电能力统计的影响因素.............................................................................................................17 4.3 发电能力统计模型的建立.............................................................................................................20 4.4 汽轮机组出力能力故障智慧树.....................................................................................................22 4.5 机组出力能力损失分析.................................................................................................................23 4.6 本章小结 ........................................................................................................................................28 第五章 核电机组发电能力计算..........................................................................................................29 5.1 二回路系统效率计算模型.............................................................................................................29 5.2 计算实例 ........................................................................................................................................32 5.3 本章小结 ........................................................................................................................................34 第六章 核电机组发电能力改进分析..................................................................................................35 6.1 基准热功率测量系统的改进.........................................................................................................35 6.2 常规岛阀门内漏检查.....................................................................................................................39 6.3 凝汽器性能维护 ............................................................................................................................42 6.4 已实施改进效果 ............................................................................................................................44 6.5 本章小结 ........................................................................................................................................46 第七章 提高机组出力能力的长期规划..............................................................................................47 7.1 岭澳机组高压缸通流问题..............................................................................................................47 7.2 低压缸入口温度高问题.................................................................................................................49 7.3 本章小结 ........................................................................................................................................53 第八章 全文总结..................................................................................................................................54 8.1 主要结论 ........................................................................................................................................54第 II 页 8.2 研究展望 ........................................................................................................................................54