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.
出处
《华中科技大学学报（城市科学版）》
CAS
2009年第4期57-61,共5页
Journal of Huazhong University of Science and Technology
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
nuclear power plant
concrete containment vessel
pro-stressed loss
concrete cracking
aging assessment
life-extending management
