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(大連理工大學(xué)建設(shè)工程學(xué)部, 大連 116024)
[摘要]ASME/ACI 359規(guī)范是美國(guó)核電廠混凝土安全殼設(shè)計(jì)的規(guī)范。介紹了ASME/ACI 359規(guī)范從開(kāi)始編制至今混凝土安全殼抗剪設(shè)計(jì)的演化過(guò)程,特別是修訂過(guò)程中進(jìn)行的混凝土板徑向剪切、切向剪切和外周剪切的試驗(yàn),論述了規(guī)范抗剪條文編寫(xiě)的科學(xué)依據(jù)和公式的來(lái)源。對(duì)編寫(xiě)和修訂我國(guó)核電廠混凝土安全殼設(shè)計(jì)規(guī)范及促進(jìn)我國(guó)混凝土安全殼的研究具有重要意義。
[關(guān)鍵詞]核電廠; 安全殼; 抗剪
中圖分類號(hào):TU37文獻(xiàn)標(biāo)識(shí)碼:A文章編號(hào):1002-848X(2018)16-0001-08
Evolution of the method for shear design of the concrete containment of nuclear power plant in American code
Gong Jinxin, Feng Zhibin, Guo Shuheng, Zhang Nailong
(Faculty of Infrastructure Engineering, Dalian University of Technology, Dalian 116024, China)
Abstract: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.
Keywords:nuclear power plant; containment; shear
作者簡(jiǎn)介:貢金鑫,博士,教授,博士研究生導(dǎo)師,Email:jinxingong@163.com。
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