美国核电厂混凝土安全壳规范抗剪设计方法的演变
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摘要
ASME/ACI 359规范是美国核电厂混凝土安全壳设计的规范。介绍了ASME/ACI 359规范从开始编制至今混凝土安全壳抗剪设计的演化过程,特别是修订过程中进行的混凝土板径向剪切、切向剪切和外周剪切的试验,论述了规范抗剪条文编写的科学依据和公式的来源。对编写和修订我国核电厂混凝土安全壳设计规范及促进我国混凝土安全壳的研究具有重要意义。
ASME/ACI 359 is the code for design of the concrete containment of nuclear power plant in United State.Introduction on evolution of ASME/ACI 359 specifications of the concrete containment shear design from the first edition to date was made,especially the tests associating with radial shear,tangential shear and peripheral shear of concrete slab during the revision process,and the source of background and philosophy of the shear design clause were discussed. It is of great significance for drafting and revising Chinese code of concrete containment of nuclear power plant as well as promoting the relevant research on the concrete containment in China.
ASME/ACI 359 is the code for design of the concrete containment of nuclear power plant in United State.Introduction on evolution of ASME/ACI 359 specifications of the concrete containment shear design from the first edition to date was made,especially the tests associating with radial shear,tangential shear and peripheral shear of concrete slab during the revision process,and the source of background and philosophy of the shear design clause were discussed. It is of great significance for drafting and revising Chinese code of concrete containment of nuclear power plant as well as promoting the relevant research on the concrete containment in China.
引文
[1]RALPH G OESTERLE,GENE CORLEY W,AHMED ELREMAILY.History of shear provisions in the ASME/ACI code for concrete reactor vessels and containments[M].London:John Wiley&Sons Ltd,2014.
[2]OESTERLE R G,RUSSELL H G.Research status and needs for shear test on large-scale reinforced concrete containment elements[J].Nuclear Engineering and Design,1982(69):187-194.
[3]OESTERLE R G.Tangential shear design in reinforced concrete containments-research results and applications[J].Nuclear Engineering and Design,1984(79):161-168.
[4]Code requirements for nuclear safety-related concrete structures and commentary:ACI 349-13[S].New York:American Concrete Institute,2013.
[5]JAU W C,WHITE R N,GERGELY P.Behavior of reinforced concrete slabs subjected to combined punching shear and biaxial tension[R],Issa Card:Cornell University,1982.
[6]ACI Committee 426.The shear strength of reinforced concrete members[J].Journal of the Structural Division,1973,99:1091-1187.
[7]HADDADIN M J,HONG S,MATTOCK A H.Stirrup effectiveness in reinforced concrete beams with axial forces[J].Journal of the Structural Division,1971,97:2277-2298.
[2]OESTERLE R G,RUSSELL H G.Research status and needs for shear test on large-scale reinforced concrete containment elements[J].Nuclear Engineering and Design,1982(69):187-194.
[3]OESTERLE R G.Tangential shear design in reinforced concrete containments-research results and applications[J].Nuclear Engineering and Design,1984(79):161-168.
[4]Code requirements for nuclear safety-related concrete structures and commentary:ACI 349-13[S].New York:American Concrete Institute,2013.
[5]JAU W C,WHITE R N,GERGELY P.Behavior of reinforced concrete slabs subjected to combined punching shear and biaxial tension[R],Issa Card:Cornell University,1982.
[6]ACI Committee 426.The shear strength of reinforced concrete members[J].Journal of the Structural Division,1973,99:1091-1187.
[7]HADDADIN M J,HONG S,MATTOCK A H.Stirrup effectiveness in reinforced concrete beams with axial forces[J].Journal of the Structural Division,1971,97:2277-2298.