田湾核电站蒸汽发生器传热管在役检查优化  

Optimization of in-service inspection of heat transfer tubes for steam generators of Tianwan nuclear power station

作　　者：彭思桐 孙玉 杨兴旺[1] 高晨 盛朝阳 PENG Sitong;SUN Yu;YANG Xingwang;GAO Chen;SHENG Chaoyang(Jiangsu Nuclear Power Corporation,Lianyungang 222042,China;Nuclear and Radiation Safety Center,MEE,Beijing 100082,China)

机构地区：[1]江苏核电有限公司,江苏连云港222042 [2]生态环境部核与辐射安全中心,北京100082

出　　处：《压力容器》2022年第12期71-77,共7页Pressure Vessel Technology

摘　　要：因田湾核电站1号机组蒸汽发生器传热管役前期间的不符合项,每次大修对传热管的抽查比例较高,使大修优化和风险控制等方面存在诸多不利影响。分析了田湾核电站1号机组蒸发器传热管降质的机理,通过对蒸汽发生器的水化学状态、二次侧腐蚀状态,蒸发器传热管涡流检查结果和缺陷扩展速率着手进行了分析和研究,并结合HAD103/07和俄罗斯相关法规标准的要求,对1号机组蒸汽发生器传热管在役检查优化的可行性进行了研究,调整制定了优化的检查方案,现场大修证实取得了良好的效果。Due to the NCR of steam generators in unit 1 of Tianwan Nuclear Power Station before being put into service, the in-service inspection proportion range of heat transfer tubes is high, there are many adverse effects on overhaul optimization and risk control.The quality degradation mechanism of evaporator heat transfer tube of unit 1 of Tianwan nuclear power station was analyzed, the hydro chemical state of steam generator, corrosion state of secondary side, eddy current inspection results of evaporator heat transfer tube and defect propagation rate were analyzed and studied, and the feasibility of optimizing in-service inspection of heat transfer tubes of steam generators in unit 1 was studied in combination with the requirements of HAD103/07 and Russian regulations and standards, and the optimized inspection scheme was adjusted and formulated.The field overhaul proved that good results were obtained.

关 键 词：蒸汽发生器 传热管 运行状态 涡流检查 缺陷扩展速率 

分 类 号：TH49[机械工程—机械制造及自动化] TK172.4[动力工程及工程热物理—热能工程] TM623.7[电气工程—电力系统及自动化]