Chemical interaction and compatibility of uranium mononitride and alumina forming austenitic stainless steel

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Andre Broussard , Dong Zhao , Kevin Yan , Bruce A. Pint , Jiheon Jun , Erofili Kardoulaki , Jie Lian
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Abstract

Uranium mononitride (UN) and alumina forming austenitic (AFA) stainless steel are a potential fuel-cladding combination for the lead-cooled fast reactor (LFR). Chemical compatibility between UN and AFA steel needs to be verified before implementation in a nuclear reactor. Diffusion couple experiments at 823 K and 1023 K were conducted for nonirradiated UN samples in contact with as-cast (no thermally grown Al2O3) and preoxidized (with thermally grown Al2O3) AFA for 500 and 1000 h in an inert environment. Preoxidized AFA exhibited little to no interaction with all UN samples tested at both 823 K and 1023 K, displaying the stability and capability of the Al2O3 layer to prevent chemical interaction and inter-diffusion with UN. Chemical interaction occurs between UN and as-cast AFA. At 1023 K, an aluminum and nitrogen rich phase (likely AlN) formed along the interface of as-cast AFA and UN samples. At 823 K the AlN phase was not prominently observed due to the reduced diffusivity of aluminum through AFA. The aluminum and nitrogen-enriched phase was also observed in a high temperature pressure-assisted test sample of UN and as-cast AFA thermally treated at 1373 K. In UN samples doped with a low weight percent of UO2 (< 3 wt%), AlN was not detected along the interface at either temperatures, and an Al2O3 layer likely formed along the interface and prevented further chemical interaction between UN and as-cast AFA.
单氮化铀和氧化铝形成奥氏体不锈钢的化学相互作用和相容性
单氮化铀(UN)和氧化铝形成奥氏体(AFA)不锈钢是一种潜在的铅冷快堆(LFR)燃料包壳组合。UN和AFA钢之间的化学相容性需要在核反应堆中实施之前进行验证。在823 K和1023 K下,对未辐照的UN样品在惰性环境中与铸态(无热生长Al2O3)和预氧化(有热生长Al2O3) AFA接触500和1000 h进行了扩散偶实验。在823 K和1023 K下,预氧化AFA与UN样品几乎没有相互作用,表明Al2O3层的稳定性和阻止UN化学相互作用和相互扩散的能力。UN和铸态AFA之间发生化学相互作用。在1023 K时,沿铸态AFA和UN试样的界面形成富铝和富氮相(可能为AlN)。在823 K时,由于铝通过AFA的扩散系数降低,AlN相不明显。在1373 K热处理的UN和铸态AFA高温压力辅助试样中也观察到富铝和富氮相。在掺有低质量百分比UO2 (<;在这两种温度下,沿界面均未检测到AlN, Al2O3层可能沿界面形成,阻止了UN和铸态AFA之间进一步的化学相互作用。
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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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