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引用次数: 2

摘要

辐射对核聚变反应堆结构性能的影响一直是影响核聚变反应堆技术发展的一个重要问题。中子辐照改变了结构部件的机械性能,导致这些性能的普遍退化。除了机械载荷(压力和重量)和热应变外,熔合结构中的辐射膨胀和蠕变也会引起非均匀的非弹性应变场。在本文中,我们描述了一个新的计算机代码,STAIRE,用于应力分析包括辐射效应。这个程序是基于标准梁理论的管道弯头。对理论进行了两方面的修正:(1)考虑了管道随曲率半径变化时的截面变形;(2)包含非弹性辐射和热应变(膨胀和蠕变)。提出了一种求解不确定梁问题的有效解析/数值方法。作为该方法的应用,对镜面先进反应堆研究(MARS)中环形覆盖管的应力分布和挠度进行了评估。膨胀应变被认为是提出的毯层设计中应力和变形的主要来源,并概述了该问题的可能解决方案。
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Inelastic structural analysis of the mars tandem mirror reactor

The effects of radiation on the structural performance of fusion reactor structures is recognized as a major issue for the development of fusion reactor technology. Neutron irradiation changes the mechanical properties of structural components resulting in a general degradation of these properties. In addition to the mechanical loads (pressure and weight) and the thermal strains, non-uniform inelastic strain fields are induced by radiation swelling and creep in fusion structures. In this paper, we describe a new computer code, STAIRE, for STress Analysis Including Radiation Effects. This code is based on standard beam theory for pipe-bends. The theory is modified in two areas: (1) consideration of the pipes' cross-section deformation as the radius of curvature changes; and (2) inclusion of inelastic radiation and thermal strains (swelling and creep). An efficient analytical/numerical approach is developed for the solution of indeterminate beam problems. As an application of the method, the stress distribution and deflections of toroidal blanket pipes in the Mirror Advanced Reactor Study (MARS) are evaluated. Swelling strains are identified as a major source of stress and deformation in the proposed blanket design, and possible solutions to the problem are outlined.

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Preface Announcement Cryopumping for fusion reactors 2.1. Development of low activation Al alloys for the R-project 6. Research and development on the tritium handling technology in the R-project
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