考虑一二回路耦合的核电站凝结水泵跳闸工况分析
Analysis of Condensate Pumptrip in Nuclear Power Plant Considering Two-Circuit Coupling
摘要: 凝结水系统是核电站二回路的主要组成部分之一,丧失凝结水会导致除氧器水位降低,进而导致给水泵跳闸,影响SG水位。核电站目前对于凝结水泵跳闸的控制策略是快速降负荷以减少核岛对主给水量的需求,稳定除氧器和SG水位。本文以先进压水堆AP1000为例,通过FLOWNEX和RELAP软件将一二回路进行耦合计算,对凝结水泵跳闸后未降负荷工况进行分析计算。计算结果表明,凝结水泵跳泵后,除氧器水位会以0.009 m/s的速率下降,在运行148 s后,给水泵由于除氧器触发低低水位而跳闸,主给水完全丧失。在主给水完全丧失后38 s (运行186 s),反应堆因SG水位低低而发生停堆。如果SG水位保护系统未响应,主给水流量与主蒸汽流量不匹配,有在主给水完全丧失之前因SG水位低低而停堆的风险。
Abstract:
The condensate system is one of the main components of the second circuit of the nuclear power plant. The loss of condensate water will cause the deaerator water level to decrease, which will cause the feed pump to trip and affect the SG water level. The current control strategy for condensate pump tripping at the nuclear power plant is to rapidly reduce the load to reduce the main water supply demand of the nuclear island and stabilize the deaerator and SG water level. Taking advanced pressurized water reactor AP1000 as an example, this paper analyzes and calculates the tripping condition of condensate pump by coupling the one-two circuit with FLOWNEX and RELAP software. The calculation results show that after the condensate pump jumps off the pump, the water level of the deaerator will drop at a rate of 0.009 m/s. After 148 s of operation, the feed pump will trip due to the low water level triggered by the deaerator, and the main water supply will be completely lost. At 186s after operation (38 s after total loss of main feed water), the reactor was shut down due to low SG water level. If the SG water level protection system is not responsive, there is a risk of shutdown due to low SG water level before the main feed is completely lost.
参考文献
|
[1]
|
龙腾. 重水堆CANDU-6机组失去两台凝泵的影响及对策[J]. 电工技术, 2019(13): 87-88. [Google Scholar] [CrossRef]
|
|
[2]
|
罗传杰, 漆向前, 周琦. 核电站凝结水泵气蚀保护的改进[J]. 广东电力, 2011, 24(4): 31-33.
|
|
[3]
|
陈海鹏. CANDU6核电厂失去凝结水故障预想及诊断[J]. 科技视界, 2015(12): 249+305. [Google Scholar] [CrossRef]
|
|
[4]
|
熊义强, 林萌, 刘鹏飞, 等. CPR1000型核电站给水泵事故瞬态分析[J]. 原子能科学技术, 2012, 46(7): 831-836.
|
|
[5]
|
温庆邦, 朱立新, 熊兴华. 核电厂满功率运行时只有一台凝结水泵运行的对策[J]. 科技展望, 2015, 25(16): 86.
|
|
[6]
|
魏承君, 于倩, 李立晓, 等. 基于FLOWNEX的AP1000常规岛热力系统全范围建模及瞬态工况模拟[J]. 科学技术与工程, 2021, 21(16): 6710-6717.
|
|
[7]
|
刘爱明. 改进型AP1000失水事故的仿真模拟[D]: [硕士学位论文]. 北京: 华北电力大学(北京), 2011.
|
|
[8]
|
张小勇, 刘琦, 杨志平, 吴志钢. AP1000核电厂二回路热力系统计算与分析[J]. 热能动力工程, 2018, 33(9): 107-113.
|
|
[9]
|
白佳琦, 杨严, 谭彭燕, 等. Flownex在循环冷却水系统仿真模拟中的应用[C]//中国建筑学会建筑给水排水研究分会. 中国建筑学会建筑给水排水研究分会第三届第一次全体会员大会暨学术交流会论文集. 2016: 867-872.
|
|
[10]
|
吴俊宏. 流体网络方法在航空发动机中的应用[C]//中国机械工程学会机械工业自动化分会、中国力学学会产学研工作委员会、中国计算机学会高性能计算专业委员会、陕西省国防科技工业信息化协会: 中国力学学会产学研工作委员会. 第十二届中国CAE工程分析技术年会论文集. 2016: 5.
|
|
[11]
|
何帆, 蔡翔舟, 郭威, 何龙, 崔蕾, 赵恒. RELAP5/FLUENT耦合程序的开发[J]. 原子能科学技术, 2021, 55(4): 693-703.
|
|
[12]
|
孙汉虹, 程平东, 缪鸿兴, 等. 第三代核电技术AP1000 [M]. 第2版. 北京: 中国电力出版社, 2016: 62-65.
|