核电站混凝土安全壳及相关设施老化特征  

AGEING CHARACTERISTICS OF CONCRETE CONTAINMENT AND ITS RELATED FACILITIES FOR NUCLEAR POWER PLANT

作　　者：万广泽 郭俊营 李忠诚 贡金鑫[1] 

机构地区：[1]大连理工大学建设工程学部土木工程学院,辽宁大连116024 [2]中广核工程设计有限公司,广东深圳518031

出　　处：《工业建筑》2017年第1期10-15,共6页Industrial Construction

基　　金：中广核集团尖峰计划安全壳状态监检测与老化管理关键技术研究项目(3100029935)

摘　　要：核电站安全壳及相关设施老化对核电站安全运营有重要影响。根据美国核管会和国际原子能组织的调查报告,对核电站安全壳及相关设施的老化特征进行了分析和总结。分析表明:安全壳混凝土最常见的老化问题为混凝土裂缝、材料剥离和孔洞;预应力系统为预应力筋锈蚀、预应力损失过大、预应力锚具开裂或失效和预应力筋孔道漏浆;内衬及钢结构构件为局部锈蚀和疲劳损伤。加强老化管理可有效提高安全壳结构的运营寿命。Ageing of concrete containment of nuclear power plants and the related facilities has an important influence on its safe operation. Based on the investigation reports prepared by the United States Nuclear Regulatory Commission and the International Atomic Energy Agency （ IAEA ）, a summary and analysis of ageing characteristics of containment and the related facilities for nuclear power plant were carried out. It was indicated that the frequent ageing problems of containment concrete were cracking, spalling and voids of concrete. For the prestressing system, the frequent ageing problems were prestressing tendon corrosion, excessive loss of prestressing force, cracking and failure of anchorages and leakage of prestressing ducts. For the liner and steel element, the frequent ageing problems were local corrosion and fatigue damage. Aging management is helpful for prolonging the service life of containments.

关 键 词：核电站 安全壳 老化特征 案例研究 

分 类 号：TU37[建筑科学—结构工程]