Citation: | Zhang Jiangtao, Du Yang, Cai Dahua, Tao Jun, Zhao Chuanli, Shi Wenxiang. Study on Creep Model of Pre-stressed Concrete Based on Component Scale[J]. Nuclear Power Engineering, 2022, 43(S1): 27-34. doi: 10.13832/j.jnpe.2022.S1.0027 |
[1] |
王晓磊,侯钢领,吕大刚. 某核电站安全壳1∶15模型振动台试验[J]. 工程力学,2014, 31(S1): 249-252,264.
|
[2] |
吴锋,卓杨,曹进捷,等. 后张法预应力混凝土管桩长期预应力损失研究[J]. 混凝土与水泥制品,2009(2): 36-37.
|
[3] |
汪建群,吕鹏,许巧,等. 混凝土徐变计算模型及其实用性评述[J]. 工程力学,2018, 35(S1): 156-160.
|
[4] |
寒秋. 混凝土收缩徐变的粘弹性随机性算法研究[D]. 北京: 北京交通大学, 2019.
|
[5] |
BAŽANT Z P, BAWEJA S. Creep and shrinkage prediction model for analysis and design of concrete structures: model B3[J]. Materials and Structures, 1995, 28(6): 357-365. doi: 10.1007/BF02473152
|
[6] |
WENDNER R, HUBLER M H, BAŽANT Z P. Statistical justification of model B4 for multi-decade concrete creep using laboratory and bridge databases and comparisons to other models[J]. Materials and Structures, 2015, 48(4): 815-833. doi: 10.1617/s11527-014-0486-1
|
[7] |
YANG M F, JIN S, GONG J X. Concrete creep analysis method based on a long-term test of prestressed concrete beam[J]. Advances in Civil Engineering, 2020, 2020: 3825403.
|
[8] |
王勋文,潘家英. 按龄期调整有效模量法中老化系数x的取值问题[J]. 中国铁道科学,1996, 17(3): 12-23.
|
[9] |
胡狄. 预应力混凝土桥梁徐变效应分析[D]. 长沙: 中南大学, 2003.
|
[10] |
高永亮. 预应力混凝土构件长期应力损失计算[D]. 长沙: 中南大学, 2014.
|
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