施工技术

2022, v.51;No.609(14) 22-26

[打印本页] [关闭]
本期目录(Current Issue) | 过刊浏览(Past Issue) | 高级检索(Advanced Search)

核电站混凝土结构抗裂施工措施研究与应用
Research and Application of Anti-crack Structural Measures for Concrete Structure of Nuclear Power Plant

文哲;李燕;李强;
WEN Zhe;LI Yan;LI Qiang;China Construction Second Engineering Bureau Co., Ltd.;

摘要(Abstract):

“华龙一号”为我国自主知识产权的第三代核电技术,核岛厂房混凝土设计强度等级通常不低于C40,结构复杂,施工难度大,且耐久性要求高,与传统的核岛工程相比在混凝土性能方面存在较大差异。结合广东太平岭核电站施工实践,通过研究,从设计、材料、施工和监测等多角度出发,在对核岛厂房结构混凝土开裂风险进行全面计算评估的基础上,以保障混凝土良好施工、力学和耐久性能为前提,对混凝土原材料与配合比进行优化设计,严格控制其胶凝材料用量,尤其是水泥用量。同时,采取水化温升控制及收缩补偿措施,并结合相关入模温度控制、分段长度划分、钢筋构造方式、保温保湿养护等施工工艺措施,最终形成应用于实际工程的核岛厂房结构混凝土裂缝控制关键技术方案并在实际工程中加以应用与完善,有效降低早期收缩开裂风险。
Hualong No.1 is the third generation nuclear power technology with independent intellectual property rights in China. The concrete design strength grade of nuclear island plant is usually no less than C40, with complex structure, difficult construction and high durability requirements. It is quite different from the traditional nuclear island project in concrete performance. Combined with the construction practice of Guangdong Taipingling Nuclear Power Plant, through research, from the perspectives of design, materials, construction and monitoring, based on the comprehensive calculation and evaluation of the structural concrete cracking risk of the nuclear island plant, and on the premise of ensuring the good construction, mechanics and durability of concrete, the design of concrete raw materials and mix proportion is optimized, and the amount of cementitious materials, especially the amount of cement is strictly controlled.At the same time, hydration temperature rise control and shrinkage compensation measures are taken, combined with relevant molding temperature control, section length division, reinforcement structure mode, thermal insulation and moisturizing maintenance and other construction process measures, and finally a key technical scheme for concrete crack control of nuclear island plant structure applied to practical projects is formed, which is applied and improved in practical projects to effectively reduce the risk of early shrinkage cracking.

关键词(KeyWords): 核电站;混凝土;抗裂构造;养护;监测;施工技术
nuclear power plant;concrete;anti-crack structure;maintenance;monitoring;construction

Abstract:

Keywords:

基金项目(Foundation): 中国建筑股份有限公司资助项目(CSCEC-2021-Z-35);; 中国建筑第二工程局有限公司资助项目(2020ZX170002)

作者(Authors): 文哲;李燕;李强;
WEN Zhe;LI Yan;LI Qiang;China Construction Second Engineering Bureau Co., Ltd.;

扩展功能
本文信息
服务与反馈
本文关键词相关文章
本文作者相关文章
中国知网
分享