核电站构筑物混凝土冻融劣化规律研究
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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.
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.
引文
[1]NAUS,D J.Concrete Component Aging and Its Significance Relative to Life Extension of Nuclear Power Plants[R].NUREG/CR-4652(ORNL/TM-10059),Martin Marietta Energy Systems,Inc.,Oak Ridge National Laboratory,Oak Ridge,TN,1986.
[2]Davis-Besse.Nuclear power station-Inspection to evaluate the root cause evaluation and corrective actions for cracking in the reinforced concrete shield building of the containment system[R].2012.
[3]IAEA-TECDOC 1025.Assessment and Management of Aging of Major Nuclear Power Plant Components Important to Safety:Concrete Containment Buildings[R].1998.
[4]廖开星,李毅.核电站安全壳混凝土结构长期预应力预测模型初步研究[J].混凝土,2015(5):140-144.
[5]汤志杰,廖开星.滨海环境安全壳混凝土氯离子侵蚀规律研究[J].混凝土,2015(5):66-69.
[6]孔祥龙,廖开星,汤志杰.碳化作用下安全壳混凝土结构耐久性研究[J].混凝土,2015(3):20-22.
[7]中华人民共和国住房和城乡建设部.GB/T 50082—2009普通混凝土长期性能和耐久性性能试验方法标准[S].北京:中国建筑工业出版社,2009.
[8]M.J.Setzer.Action of Frost and Deicing Chemicals:Basic Phenomena and Testing[C].Freeze-Thaw Durability of Concrete,1997.
[9]刘志勇,马立国.高强混凝土的抗冻性与寿命预测模型[J].工业建筑,2005,35(1):11-14.
[10]李金玉,邓正刚,曹建国,等.混凝土抗冻性的定量化设计[A]//王媛俐,姚燕.重点工程混凝土耐久性的研究与工程应用[M].北京:中国建材工业出版社,2001:265-272.
[11]林迟,欧进萍.基于结构全寿命设计需求的冻融作用谱模型与参数[J].自然灾害学报,2013(8):1-10.
[2]Davis-Besse.Nuclear power station-Inspection to evaluate the root cause evaluation and corrective actions for cracking in the reinforced concrete shield building of the containment system[R].2012.
[3]IAEA-TECDOC 1025.Assessment and Management of Aging of Major Nuclear Power Plant Components Important to Safety:Concrete Containment Buildings[R].1998.
[4]廖开星,李毅.核电站安全壳混凝土结构长期预应力预测模型初步研究[J].混凝土,2015(5):140-144.
[5]汤志杰,廖开星.滨海环境安全壳混凝土氯离子侵蚀规律研究[J].混凝土,2015(5):66-69.
[6]孔祥龙,廖开星,汤志杰.碳化作用下安全壳混凝土结构耐久性研究[J].混凝土,2015(3):20-22.
[7]中华人民共和国住房和城乡建设部.GB/T 50082—2009普通混凝土长期性能和耐久性性能试验方法标准[S].北京:中国建筑工业出版社,2009.
[8]M.J.Setzer.Action of Frost and Deicing Chemicals:Basic Phenomena and Testing[C].Freeze-Thaw Durability of Concrete,1997.
[9]刘志勇,马立国.高强混凝土的抗冻性与寿命预测模型[J].工业建筑,2005,35(1):11-14.
[10]李金玉,邓正刚,曹建国,等.混凝土抗冻性的定量化设计[A]//王媛俐,姚燕.重点工程混凝土耐久性的研究与工程应用[M].北京:中国建材工业出版社,2001:265-272.
[11]林迟,欧进萍.基于结构全寿命设计需求的冻融作用谱模型与参数[J].自然灾害学报,2013(8):1-10.