Erofili Kardoulaki , Maria Kosmidou , Jason Rizk , Darrin Byler , Nan Li , Arne Croell , Jamelle K.P. Williams , Jhonathan Rosales , Kenneth J. McClellan , Sven C. Vogel
{"title":"Assessment of the hydrogen resistance of (U0.2Zr0.8)C following exposure up to 2327 °C","authors":"Erofili Kardoulaki , Maria Kosmidou , Jason Rizk , Darrin Byler , Nan Li , Arne Croell , Jamelle K.P. Williams , Jhonathan Rosales , Kenneth J. McClellan , Sven C. Vogel","doi":"10.1016/j.ceramint.2025.02.218","DOIUrl":null,"url":null,"abstract":"<div><div>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 (U<sub>0.2</sub>Zr<sub>0.8</sub>)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 <span><math><mrow><mo>±</mo></mrow></math></span> 2.98 <span><math><mrow><mi>μ</mi></mrow></math></span> m, hydrogen exposed: 8.6 <span><math><mrow><mo>±</mo></mrow></math></span> 2.71 <span><math><mrow><mi>μ</mi></mrow></math></span> 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 (U<sub>0.2</sub>Zr<sub>0.8</sub>)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.</div></div>","PeriodicalId":267,"journal":{"name":"Ceramics International","volume":"51 15","pages":"Pages 20482-20491"},"PeriodicalIF":5.1000,"publicationDate":"2025-06-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Ceramics International","FirstCategoryId":"88","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0272884225009010","RegionNum":2,"RegionCategory":"材料科学","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"MATERIALS SCIENCE, CERAMICS","Score":null,"Total":0}
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 m, hydrogen exposed: 8.6 2.71 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.
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.