不同功率水平下压水堆核电机组甩负荷保护研究Research on Load Rejection Protection of Pressurized Water Reactor Nuclear Power Units Under Different Power Levels
文立斌;李俊;孙艳;张翌晖;刘光时;
摘要(Abstract):
甩负荷特性是衡量核电机组安全稳定运行能力的重要标准,因而甩负荷试验是压水堆(pressurized water reactor,PWR)核电厂调试阶段必不可少的试验项目,在不同功率水平下运行的核电机组表现出不同的甩负荷特性。根据核电机组的实际运行特性,建立压水堆核电机组模型,仿真模拟多种功率水平下核电机组的甩负荷工况。在此基础上加入旁路蒸汽排放系统和汽门快关系统,对压水堆核电机组的甩负荷保护进行研究。仿真结果表明,功率水平越高,机组甩负荷引起的扰动越大,必须装设保护系统;旁路蒸汽排放系统和汽门快关系统都能够对核电机组产生有效的保护作用,前者对核电机组反应堆、热力系统参数保护作用较显著,后者对汽轮机转速飞升抑制作用较显著。
关键词(KeyWords): 压水堆核电机组;甩负荷保护;功率水平;旁路蒸汽排放系统;汽门快关系统
基金项目(Foundation): 中国南方电网公司科技项目:核电机组动态模型开发及与电网的相互作用特性研究(GXKJXM20160002)~~
作者(Author): 文立斌;李俊;孙艳;张翌晖;刘光时;
Email:
DOI: 10.13335/j.1000-3673.pst.2018.2300
参考文献(References):
- [1]钟磊,欧阳利平,蔡红霞,等.大型核电机组接入电网的稳定性研究[J].浙江电力,2013(11):15-18.Zhong Lei,Ouyang Liping,Cai Hongxia,et al.Investigation on stability of large-scale nuclear power units connected to the grid[J].Zhejiang Electric Power,2013(11):15-18(in Chinese).
- [2]Peters S,Machnida G T,Nthontho M,et al.Modelling and simulation of degraded and loss of voltage protection scheme for class 1E bus of a nuclear power plant[C]//Universities Power Engineering Conference.London,United Kingdom:IEEE,2012.
- [3]赵洁,刘涤尘,杨楠,等.核电机组参与电网调峰的运行方式及效益分析[J].电网技术,2012,36(12):250-255.Zhao Jie,Liu Dichen,Yang Nan,et al.Operation mode and benefits of nuclear power plant participating in peak load regulation of power system[J].Power System Technology,2012,36(12):250-255(in Chinese).
- [4]张学成,胡学浩,周修铭,等.具有核电模型的中期动态模拟程序开发及大型核站与电力系统相互影响的研究[J].电网技术,1995,19(2):5-10.Zhang Xuecheng,Hu Xuehao,Zhou Xiuming,et al.Development of midterm dynamic simulation program including nuclear power plant model and study of interaction between large nuclear power plant and power system[J].Power System Technology,1995,19(2):5-10(in Chinese).
- [5]廖诗武,曾凯文,姚伟,等.火电快速甩负荷机组动态仿真建模[J].电工技术学报,2017,32(4):212-220.Liao Shiwu,Zeng Kaiwen,Yao Wei,et al.Dynamic model for thermal units with fast cut back function[J].Transaction of China Electronical Society,2017,32(4):212-220(in Chinese).
- [6]王立地,姚金环.FCB功能的成功应用与一种新的实现方案[J].自动化仪表,2004,25(6):48-52.Wang Lidi,Yao Jinhuan.Successful application of FCB and new implementation strategy[J].Process Automation Instrumentation,2004,25(6):48-52(in Chinese).
- [7]冯伟忠.1000MW级火电机组旁路系统作用及配置[J].中国电力,2005,38(8):53-56.Feng Weizhong.Function and configuration of bypass system for1000MW class thermal power unit[J].Electric Power,2005,38(8):53-56(in Chinese).
- [8]吴文超,王子奇,等.AP1000汽轮发电机组甩负荷试验研究[J].中国核电,2015,8(1):19-23.Wu Wenchao,Wang Ziqi,et al.Analysis of turbine load shedding test for AP1000 nuclear power plant[J].China Nuclear Power,2015,8(1):19-23(in Chinese).
- [9]周修铭,干福麟,衷文华,等.适用于分析大扰动下机网相互影响的压水堆核电站数学模型研究[J].核动力工程,1996(1):6-12.Zhou Xiuming,Gan Fulin,Zhong Wenhua,et al.The mathematical model of PWR nuclear power plant applied to analyze the interaction of large disturbance networks[J].Nuclear Power Engineering,1996(1):6-12(in Chinese).
- [10]王梦,丁剑,吴国旸,等.考虑核电接入的大电网严重故障下孤网高频问题及协调控制措施[J].电力自动化设备,2015,35(12):101-107.Wang Meng,Ding Jian,Wu Guoyang,et al.High frequency problems and coordinated control measures of isolated network under serious power grid failure considering nuclear power access[J].Electric Power Automation Equipment,2015,35(12):101-107(in Chinese).
- [11]高慧敏,孙蓉,徐政.田湾核电机组动态模型研究及其对江苏电网系统扰动的响应分析[J].华东电力,2006,34(5):6-10.Gao Huimin,Sun Rong,Xu Zheng.Dynamic models of Tianwan nuclear units and their response to system disturbances of Jiangsu Power Grid[J].East China Electric Power,2006,34(5):6-10(in Chinese).
- [12]王宝生,王冬青,张建民,等.压水堆核电厂蒸汽排放控制系统实时仿真研究[J].核动力工程,2011,32(5):38-44.Wang Baosheng,Wang Dongqing,Zhang Jianmin,et al.Real-time simulation of steam emission control system of PWR power plant[J].Nucelar Power Engineering,2011,32(5):38-44(in Chinese).
- [13]朱军.某核电厂甩负荷孤岛运行试验及问题分析[J].硅谷,2014(23):245-246.Zhu Jun.Operation test and problem analysis of load rejection in a nuclear power plant[J].Silicon Valley,2014(23):245-246(in Chinese).
- [14]胡彦令.M310核电机组调试前准备过程探究[J].工业技术创新,2017,4(1):152-154.Hu Yanling.Research on the preparation process before commissioning nuclear power units[J].Industrial Technology Innovation,2017,4(1):152-154(in Chinese).
- [15]刘庆,吴国旸,宋新立,等.适用于电网稳定分析的大容量核电机组建模[J].电网技术,2017,41(3):907-914.Liu Qing,Wu Guoyang,Song Xinli,et al.Modeling of large-capacity nuclear power unit suitable for power grid stability analysis[J].Power System Technology,2017,41(3):907-914(in Chinese).
- [16]Kerlin T W,Katz E M.Pressurized-water-reactor modeling for long-term power system dynamics simulations[R].California:EPRIFinal Report EL-3087:1983.
- [17]Podowski M.A study of nuclear reactor models with nonlinear reactivity feedbacks:Stability criteria and power overshoot evaluation[J].IEEE Transactions on Automatic Control,1986,31(2),108-115.
- [18]赵洁,刘涤尘,吴耀文.压水堆核电厂接入电力系统建模[J].中国电机工程学报,2009,29(31):8-13.Zhao Jie,Liu Dichen,Wu Yaowen.Modelling of pressurized water reactor nuclear power plant integrated into power system simulation[J].Proceedings of the CSEE,2009,29(31):8-13(in Chinese).
- [19]张学成.用于电力系统动态模拟的压水堆核电站数学模型[J].电网技术,1990(4):71-77.Zhang Xuecheng.The mathematical model of PWR nuclear power plant for dynamic simulation of power system[J].Power System Technology,1990(4):71-77(in Chinese).
- [20]葛斌,张俊礼.核电机组二回路建模与动态仿真[J].电力自动化设备,2012,32(6):76-79.Ge Bin,Zhang Junli.Dynamic modeling simulation of nuclear power unit secondary circuit[J].Electric Power System Automation Equipment,2012,32(6):76-79(in Chinese).
- [21]吴萍,杨艳晨,陈昊,等.第三代核电堆型AP1000运行特点及堆芯仿真研究[J].电网技术,2014,38(5):1196-1202.Wu Ping,Yang Yanchen,Chen Hao,et al.Research on operational characteristics and core simulation of the third-generation nuclear reactor AP1000[J].Power System Technology,2014,38(5):1196-1202(in Chinese).