Assessment of the hydrogen resistance of (U0.2Zr0.8)C following exposure up to 2327 °C

IF 5.1 2区 材料科学 Q1 MATERIALS SCIENCE, CERAMICS
Erofili Kardoulaki , Maria Kosmidou , Jason Rizk , Darrin Byler , Nan Li , Arne Croell , Jamelle K.P. Williams , Jhonathan Rosales , Kenneth J. McClellan , Sven C. Vogel
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引用次数: 0

Abstract

Nuclear fuels able to withstand hydrogen exposure >2227 °C with minimal chemical and mechanical changes are required to enable nuclear thermal propulsion reactors for deep space exploration. Previously (U0.2Zr0.8)C was demonstrated to exhibit minimal mass loss, while maintaining structural integrity, when exposed to hydrogen at 2327 °C for 3 h. Here, various techniques were implemented for an in-depth characterization of that same sample. X-ray and neutron diffraction were used to assess for formation of secondary phases and to examine lattice parameter changes on the surface and the bulk of the material by probing the full volume of the 8 × 8 × 12 mm sample. In addition, nano-indentation and microstructural characterization were conducted to understand the impact of hydrogen exposure to the mechanical properties and internal microstructure of the material. The results indicate that: 1) no new phases were observed throughout the volume of the hydrogen-exposed sample, nor any lattice parameter evolution was reported suggesting the composition of the sample following hydrogen exposure remained unchanged; 2) the microstructure was not significantly altered, although a small reduction in the grain size (as-fabricated: 12.9 ± 2.98 μ m, hydrogen exposed: 8.6 ± 2.71 μ m) and an increase in porosity (as-fabricated: 97.82 % theoretical density (TD), hydrogen exposed: 89.31 % TD) were observed; 3) the hardness of the hydrogen-exposed material did increase by ∼8.5 % when compared to the as-fabricated material and the hardness of the hydrogen exposed sample was shown to decrease with increasing temperature, as expected based on experience with ZrC. This detailed post-characterization examination, which is the first of its kind for fuels exposed to pure hydrogen at 2327 °C, suggests (U0.2Zr0.8)C would be incredibly resistant against chemical, dimensional, and mechanical changes when exposed to high temperature hydrogen during operation of a nuclear thermal propulsion reactor, making it an attractive fuel choice.
(U0.2Zr0.8)C暴露至2327°C后的耐氢性评估
为了使核热推进反应堆能够用于深空探测,需要能够承受2227°C的氢暴露,并且化学和机械变化最小的核燃料。先前(U0.2Zr0.8)C在2327°C下暴露于氢3小时时,表现出最小的质量损失,同时保持结构完整性。这里,采用各种技术对同一样品进行深入表征。通过探测8 × 8 × 12 mm样品的完整体积,利用x射线和中子衍射来评估二次相的形成,并检查材料表面和体积上的晶格参数变化。此外,还进行了纳米压痕和微观结构表征,以了解氢暴露对材料力学性能和内部微观结构的影响。结果表明:1)氢暴露后的样品在整个体积内没有发现新的相,晶格参数的变化也表明氢暴露后样品的组成没有变化;2)显微组织变化不大,但晶粒尺寸略有减小(制备态:12.9±2.98 μ m,氢暴露态:8.6±2.71 μ m),孔隙率略有增加(制备态:97.82%理论密度,氢暴露态:89.31%理论密度);3)与制备的材料相比,氢暴露材料的硬度确实增加了~ 8.5%,并且氢暴露样品的硬度随着温度的升高而降低,这是基于ZrC的经验所期望的。这项详细的后表征研究是首次对暴露在2327°C纯氢中的燃料进行的此类研究,表明(U0.2Zr0.8)C在核热推进反应堆运行过程中暴露在高温氢中时,对化学、尺寸和机械变化具有令人难以置信的抵抗力,使其成为一种有吸引力的燃料选择。
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来源期刊
Ceramics International
Ceramics International 工程技术-材料科学:硅酸盐
CiteScore
9.40
自引率
15.40%
发文量
4558
审稿时长
25 days
期刊介绍: Ceramics International covers the science of advanced ceramic materials. The journal encourages contributions that demonstrate how an understanding of the basic chemical and physical phenomena may direct materials design and stimulate ideas for new or improved processing techniques, in order to obtain materials with desired structural features and properties. Ceramics International covers oxide and non-oxide ceramics, functional glasses, glass ceramics, amorphous inorganic non-metallic materials (and their combinations with metal and organic materials), in the form of particulates, dense or porous bodies, thin/thick films and laminated, graded and composite structures. Process related topics such as ceramic-ceramic joints or joining ceramics with dissimilar materials, as well as surface finishing and conditioning are also covered. Besides traditional processing techniques, manufacturing routes of interest include innovative procedures benefiting from externally applied stresses, electromagnetic fields and energetic beams, as well as top-down and self-assembly nanotechnology approaches. In addition, the journal welcomes submissions on bio-inspired and bio-enabled materials designs, experimentally validated multi scale modelling and simulation for materials design, and the use of the most advanced chemical and physical characterization techniques of structure, properties and behaviour. Technologically relevant low-dimensional systems are a particular focus of Ceramics International. These include 0, 1 and 2-D nanomaterials (also covering CNTs, graphene and related materials, and diamond-like carbons), their nanocomposites, as well as nano-hybrids and hierarchical multifunctional nanostructures that might integrate molecular, biological and electronic components.
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