核电站构筑物混凝土冻融劣化规律研究  

Research on Freeze-thaw Damage Degradation Rules of Concrete of Nuclear Power Plant

作　　者：汤志杰[1] 廖开星 孔祥龙[1] 李毅[1] 徐超[1] 

机构地区：[1]苏州热工研究院有限公司寿命中心老化管理技术研究所,215004

出　　处：《混凝土与水泥制品》2017年第4期13-16,共4页China Concrete and Cement Products

基　　金：中国广核集团科研项目(尖峰计划)

摘　　要：以核电站构筑物混凝土为研究对象进行了快速冻融试验,分别研究分析了混凝土冻融损伤后的宏观性能及冻融前后混凝土的孔隙结构变化。基于相对动弹性模量提出了混凝土冻融损伤分段式模型,拟合精度较高。并以某北方核电站为例,评估了构筑物混凝土结构的使用寿命为229年,结果符合工程实际情况。The fast freeze-thaw tests are carried on for concrete of nuclear power plant structures. The macroscopic properties and pore structure of concrete samples were studied and analyzed before and after freeze-thaw tests. Freeze- thaw damage sectional model is put forward based on the relative dynamic elastic modulus, high fitting precision is achieved. Taking one northern nuclear power plant as an example, the service life of concrete structures is calculated, the result is accorded with actual situation.

关 键 词：核电站构筑物 混凝土 冻融 寿命预测 

分 类 号：TU528.01[建筑科学—建筑技术科学]