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Structural response of nuclear containment shield buildings with unanticipated construction openings.

机译:具有未预期的施工开口的核安全壳防护建筑物的结构响应。

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摘要

As Nuclear Power Plants age many require steam generator replacement. There is a nickel alloy in the steam generator tubes that is susceptible to stress cracking and although these cracks can be sealed the generator becomes uneconomical without 10%-15% of the tubes. The steam generator in a typical nuclear power plant is housed in the containment structure next to the reactor. The equipment hatch is not big enough to facilitate steam generator replacement, thus construction openings in the dome of the containment structure are required.; To date the structural consequences of construction openings in the dome have not been examined. This thesis examines the effects of such openings. The prototype concrete dome is made up of a 2 ft thick dome atop 3 ft thick and 170 ft high cylindrical walls (radius 65.5 ft) with a tension ring 15 ft high and 8 ft thick in between. The dome of the building is cast in two layers; a lower 9 inch layer that serves as the formwork for an upper 15 inch layer. The weight of the dome is carried in axial compression along the hoops and meridians of the dome.; The first finite element model uses shell elements and considers two limiting load cases; where the two layers act as one, and where the lower layer carries the weight of both. The openings interrupt the hoops and meridians and the weight of the dome must be redistributed around the openings. Without openings, the stresses due to dead load in the structure are very low when compared to the material strength. The impact of the openings is increased compression stresses near the opening. The maximum stresses are approximately four times larger than in the original structure. These results are confirmed by the second model which is made from layers of solid elements. This model shows a significant difference between the compression on the top surface of the dome, in the affected areas, and that on the bottom surface, leading to shear stresses. These shear stresses are largest around the opening but are not large enough to cause delamination.
机译:随着核电站的老化,许多需要更换蒸汽发生器。蒸汽发生器管道中存在一种镍合金,该镍合金易于应力开裂,尽管这些裂缝可以被密封,但如果没有10%-15%的管道,发生器将变得不经济。典型核电站中的蒸汽发生器位于反应堆旁的安全壳结构中。设备舱口的尺寸不足以方便蒸汽发生器的更换,因此,需要在安全壳结构的圆顶内设置开口。迄今为止,尚未检查圆顶中的建筑开口的结构后果。本文研究了这种开口的影响。原型混凝土圆顶由3英尺厚,170英尺高的圆柱壁(半径65.5英尺)顶上的2英尺厚的圆顶以及介于15英尺高和8英尺厚之间的拉力环组成。建筑物的圆顶分为两层。下部9英寸层用作上部15英寸层的模板。穹顶的重量沿穹顶的环和子午线轴向压缩。第一个有限元模型使用壳单元并考虑两个极限载荷工况。两层合为一体,而下层则承担了两者的重量。开口打断了铁环和子午线,圆顶的重量必须在开口周围重新分配。如果没有开口,与材料强度相比,由于结构中的恒载而产生的应力非常低。开口的影响是开口附近的压缩应力增加。最大应力约为原始结构的四倍。这些结果由第二个模型确定,该模型由固体元素层制成。该模型显示了穹顶顶表面,受影响区域中的压缩与底表面上的压缩之间的显着差异,从而导致剪切应力。这些剪切应力在开口周围最大,但不足以引起分层。

著录项

  • 作者单位

    Princeton University.;

  • 授予单位 Princeton University.;
  • 学科 Engineering Civil.; Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2007
  • 页码 114 p.
  • 总页数 114
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 建筑科学;原子能技术;
  • 关键词

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