核电站预应力混凝土安全壳的老化因素研究  

Aging Factors of Prestressed Concrete Containment Vessel in Nuclear Power Plant

作　　者：郑砚国[1,2,3] 李惠强[1,2] 

机构地区：[1]华中科技大学土木工程与力学学院 [2]华中科技大学控制结构湖北省重点实验室,湖北武汉430074 [3]中核集团湖南桃花江核电有限公司,湖南益阳413000

出　　处：《华中科技大学学报（城市科学版）》2009年第4期57-61,共5页Journal of Huazhong University of Science and Technology

摘　　要：核电站预应力混凝土安全壳设计寿命目前多为40年,加强安全壳结构的在役检查,评估其老化状态,是保障安全壳正常工作及判断能否延长其使用寿命的前提。本文探讨建立安全壳延寿管理工作体系;对安全壳混凝土材料的碳化、氯离子侵入、碱-骨料反应、开裂机理、钢绞线的预应力损失、安全壳钢板衬里锈蚀等老化因素进行了较全面分析;对如何缓解核电站混凝土安全壳老化提出了一些建议。The design life of prestressed concrete containment vessel of nuclear power plant is 40 years now. Enhancing in-service inspection of the containment vessel and assessing its aging state are the premise of protection the containment vessel to work safety and judgment extending its life. The paper discussed the life-extending management system of the containment vessel, and analyzed the aging factors, including the concrete carbonation, chloride ion ingress, alkali-aggregate reaction, cracking mechanism, pre-stressed loss in the steel strands, and corrosion of the steel liner, and so on. Some suggestions were proposed to relieve the aging of the containment vessel.

关 键 词：核电站 混凝土安全壳 预应力损失 混凝土开裂 老化评估 延寿管理 

分 类 号：TU378[建筑科学—结构工程] TU271.5