评估用于评估核结构材料和快速成型材料的新型亚尺寸拉伸试样几何形状的可行性

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
David Collins , Maxim Gussev , Stephen Taller , T.S. Byun , Caleb Massey
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引用次数: 0

摘要

由于辐射安全问题和资源保护需要,在核材料试验中使用亚尺寸标本一直是一个令人感兴趣的问题。它也对增材制造(AM)感兴趣,也称为3d打印,因为子尺寸样品可以更准确地代表通常使用AM生产的小型复杂几何形状的行为。最近开发了一种新颖的、极小的几何形状,称为Subsize Teeny (SST),对实现很感兴趣。考虑到其非常小的尺寸和与亚尺寸样品测试相关的复杂性,对这种几何形状进行充分的审查是必要的,以确保数据质量。各种未辐照的核结构材料在SST几何结构中进行了测试,并与已建立的SSJ3几何结构进行了比较。此外,还进行了两个案例研究,将SST作为增材制造材料的筛选几何结构。SST可行性的问题被发现是非常微妙的,并且通常取决于所讨论的上下文或应用。然而,确定SST在很大程度上是一种无效的几何形状,用于异常粗粒度的材料,或者在物理缺陷体积等于或超过0.1%的情况下,或者在样品加工参数导致重大表面变化的情况下。另一方面,如果测试材料几乎或完全没有物理缺陷,各向同性,表现出均匀的塑性变形,并且具有细粒,几乎或完全均匀的微观结构,至少有12个滑移系统,则确定SST可以可靠地使用。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Assessing the viability of a new subsize tensile specimen geometry for evaluation of structural nuclear and additively manufactured materials
The use of subsize specimens in nuclear materials testing has been a subject of ongoing interest due to radiation safety concerns and resource conservation needs. It is also of interest in additive manufacturing (AM), also known as 3D-printing, as subsize specimens can more accurately represent the behavior of the small, intricate geometries often produced using AM. A novel, extremely small geometry, called the Subsize Teeny (SST) was recently developed and is of interest for implementation. Given its extraordinarily small size and the complexities associated with subsize specimen testing, adequate vetting of this geometry is necessary to ensure data quality. A variety of unirradiated nuclear structural materials were tested in the SST geometry and compared against the well-established SSJ3 geometry. In addition, two case studies implementing the SST as a screening geometry for AM materials were also conducted. The question of SST viability was found to be highly nuanced and will often be dependent on the context or application in question. It was determined, however, that the SST is a largely invalid geometry for exceptionally coarse-grained materials or in cases where the physical defect volume equals or exceeds 0.1 % or where the specimen machining parameters result in significant surface alterations. On the other hand, it was determined that the SST may be employed with confidence if the test material is nearly or totally free of physical defects, isotropic, demonstrates homogeneous plastic deformation, and possesses a fine-grained, nearly or totally homogeneous microstructure with at least twelve slip systems.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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