Assessing Prestress Losses in a Nuclear Containment Structure for License Renewal

Eric Kjolsing, R. James, Keith Kubischta, D. Parker
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Abstract

Nuclear power plants around the world are nearing the end of their designed service life. Sufficient structural capacity must be demonstrated to extend each plant’s operating license when accounting for concrete creep, shrinkage, and tendon relaxation past the original design life. This may take the form of in-situ values which meet the design allowable or, as outlined in this paper, analysis models which demonstrate capacity. This paper presents an analysis methodology for a concrete containment structure utilizing grouted post-tensioned tendons representative of a non-US design. The methodology is intended to demonstrate that a structure can still meet established design requirements while accounting for creep, shrinkage, and tendon relaxation. The analysis effort is performed in multiple stages. First, design parameters feeding into post-tensioning loss calculations are identified and assigned statistical distributions. Probabilistic estimates of the post-tensioning losses are developed using both a variational and Monte Carlo approach. Second, a finite element model of a representative containment structure is developed with tendons and reinforcement explicitly modeled. Lastly, the finite element model is used in example analyses to demonstrate future performance and pressure capacity accounting for projected tendon losses.
为许可证更新评估核安全壳结构的预应力损失
世界各地的核电站正接近其设计使用寿命的终点。考虑到混凝土徐变、收缩和肌腱松弛超过了最初的设计寿命,必须证明有足够的结构能力来延长每个工厂的运营许可证。这可以采用满足设计允许值的原位值的形式,或者如本文所述,采用展示能力的分析模型。本文提出了一种分析方法,为一个混凝土围护结构利用灌浆后张预应力筋代表非美国设计。该方法旨在证明,在考虑蠕变、收缩和肌腱松弛的情况下,结构仍然可以满足既定的设计要求。分析工作分多个阶段进行。首先,确定用于后张拉损失计算的设计参数并分配统计分布。用变分法和蒙特卡罗法对张拉后损失进行概率估计。其次,建立了具有代表性的围护结构的有限元模型,并对其筋和筋进行了明确的建模。最后,在实例分析中使用有限元模型来演示考虑预计肌腱损失的未来性能和压力能力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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