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Response Simulation of 1/4 Scale Prestressed Concrete Containment Vessel Model

机译:1/4比例预应力混凝土安全壳模型的响应模拟

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摘要

Under the ultimate internal pressure the nuclear reactor containment exhibits non-symmetrical and non-linear behavior.This is due to the structure having non-symmetric factors such as buttresses, penetrations and tendon layout in the dome.Therefore, the behavior of the structure under ultimate pressure should be assessed with a three dimensional model whichconsiders the non-symmetry. In this study, an assessment method using the 3D global model is proposed. In order to simulatethe real behavior of the prestressed concrete containment vessel, two numerical models - an axisymmetric model and a threedimensionmodel - are refined by comparison of the analysis results and with existing research results. In the analysis ofprestressed concrete containment, exhibiting highly nonlinear behavior, both Menetrey-Willam' s concrete failure criteria andmodified Drucker-Prager' s concrete failure criteria are introduced to the finite element models. In accordance with Smith' sresearch results, non-associated plastic flow rules are applied for the concrete material model.
机译:在极限内部压力下,核反应堆的安全壳表现出不对称和非线性的行为,这是由于结构具有穹顶中的支撑,穿透和腱布置等非对称因素的缘故。极限压力应使用考虑非对称性的三维模型进行评估。在这项研究中,提出了一种使用3D全局模型的评估方法。为了模拟预应力混凝土安全壳的真实行为,通过比较分析结果和现有研究结果,完善了两个数值模型-轴对称模型和三维模型。在分析预应力混凝土密闭性表现出高度非线性的行为时,将Menetrey-Willam的混凝土破坏准则和修正的Drucker-Prager的混凝土破坏准则引入了有限元模型。根据史密斯的研究结果,将非关联塑性流动规则应用于混凝土材料模型。

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  • 来源
    《》|2001年|p.1-7|共7页
  • 会议地点 Washington DC(US);Washington DC(US)
  • 作者

    Nam-Ho Lee; I1-Hwan Moon;

  • 作者单位

    Department of Civil/Architectural Engineering Korea Power Engineering Company Yongin-si Korea;

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