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Overview of fatigue life assessment of baffles in Wendelstein 7-X

机译:挡板的疲劳寿命评估概述在Wendelstein 7-X中

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Wendelstein 7-X (W7-X), the world’s largest nuclear fusion experiment of modular stellarator type, started operation in 2015 and will be upgraded with a water cooled first wall for steady state operation in 2020. The first wall consists of a CFC armored island divertors, adjacent baffles, heat shields, and stainless steel wall panels. Baffle and heat shield segments consist of graphite tiles, bolted with low pre-stress onto heat sinks of CuCrZr that are in turn brazed onto water cooled steel pipes.Cracks were detected before installation in the baffles in the root of the brazed seam in over 100 locations. Such cracks are attributed to the imposed plastic deformation of the pipes to bring them into the final shape following the complex 3D geometry of the plasma vessel.This paper gives an overview of the experimental and numerical work using finite element method (FEM) and dual boundary element method (DBEM), including sub-modeling to assess the risk of a water leak during operation. Details of the numerical work is published in Giannella et al. (2017), Lepore et al. (2017) and Citarella et al. (2018).First fatigue crack growth experiments were carried out on pipe material and thermal-mechanical crack growth predictions were made with FEM and DBEM. It appeared that the Stress Intensity Factor (SIF) threshold of the ductile steel is only reached when large plastic strains occur, thus violating the field of application of linear elastic fracture mechanics to forecast crack growth.Afterwards, representative brazed pipe samples were manufactured and subjected to initial plastic deformation causing cracks in 11 out of 12 samples. Some samples were tested up to 60,000 bending load cycles. Two out of four samples failed after ∼35,000 cycles. Before and after the test, the shape of the cracks was measured using 3D computer tomography scans. Equivalence between thermal load in W7-X and the mechanical load in the cyclic test was determined with the numerical models to allow for a prediction of the fatigue life in W7X. Additional modeling showed that also plastic zones away from the cracks can limit the fatigue life.
机译:Wendelstein 7-X(W7-X)是世界上最大的模块化恒星型核聚变实验,于2015年开始运行,并将于2020年升级为水冷第一壁以实现稳态运行。第一壁由CFC装甲组成岛式偏滤器,相邻的挡板,隔热罩和不锈钢墙板。挡板和热屏蔽段由石墨砖组成,用低预应力将其螺栓连接到CuCrZr散热器上,然后将其钎焊到水冷钢管上。在将钎焊板的根部安装到挡板中之前,已检测到裂纹位置。此类裂纹归因于管道的塑性变形,使其遵循等离子容器的复杂3D几何形状而成为最终形状。本文概述了使用有限元方法(FEM)和双重边界进行的实验和数值研究有限元方法(DBEM),包括子模型以评估操作期间漏水的风险。数值工作的详细信息发表在Giannella等人的文章中。 (2017),Lepore等。 (2017)和Citarella等。 (2018)。首次对管道材料进行了疲劳裂纹扩展实验,并使用FEM和DBEM进行了热机械裂纹扩展的预测。似乎只有在发生大的塑性应变时才达到球墨铸钢的应力强度因子(SIF)阈值,从而违反了线性弹性断裂力学在预测裂纹扩展方面的应用领域。最初的塑性变形会导致12个样品中的11个产生裂纹。对某些样品进行了高达60,000个弯曲载荷循环的测试。约35,000次循环后,四分之二的样本失败。在测试之前和之后,使用3D计算机断层扫描技术测量裂纹的形状。使用数值模型确定W7-X中的热负荷与循环测试中的机械负荷之间的等价关系,以便预测W7X中的疲劳寿命。附加的模型表明,远离裂纹的塑料区域也会限制疲劳寿命。

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