相分解对 WCrY SMART 材料机械性能和抗氧化性的影响

IF 2.3 2区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Materials and Energy Pub Date : 2024-10-10 DOI:10.1016/j.nme.2024.101762
Jie Chen , Elena Tejado , Andrey Litnovsky , Duc Nguyen-Manh , Eric Prestat , Tamsin Whitfield , Jose Ygnacio Pastor , Martin Bram , Jan Willem Coenen , Christian Linsmeier , Jesus Gonzalez-Julian
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引用次数: 0

摘要

自钝化 W-11.4Cr-0.6Y (重量百分比)合金是核聚变电站中一种等离子体面候选装甲材料。在本研究中,通过球磨和现场辅助烧结工艺制作的烧结材料在 1000 °C 下进行了持续时间不等的退火,以诱导相分解。这一过程导致最初均匀的微观结构转变为两种不同的相:富含 W 的相(αW,Cr)和富含 Cr 的相(αCr,W)。富铬相优先在晶界(钇氧化物也位于晶界)形成,并随着退火时间的延长逐渐粗化至亚微米范围。退火 75 小时后,两相的化学成分保持相对稳定。与烧结状态相比,100 小时退火后的材料在室温下表现出明显的软化,在所有测试温度下的抗弯强度都有所提高,但在高温下的断裂韧性较低。在 1000 °C 的潮湿空气中,经过 100 小时退火处理的材料的氧化行为在其 TGA 曲线中显示出两个阶段:内部氧化层的初始增长和随后保护铬层的发展。相比之下,原烧结材料在整个氧化过程中呈现出持续的线性质量增长。这些研究结果表明,分解微结构在第一壁应用方面前景广阔。
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Influence of phase decomposition on mechanical properties and oxidation resistance of WCrY SMART material
Self-passivating W-11.4Cr-0.6Y (in wt.%) alloy is a plasma-facing candidate armour material in fusion power plants. In the present work, the as-sintered material, fabricated via ball milling and field-assisted sintering, was annealed at 1000 °C for varying durations to induce phase decomposition. This process leads to the transformation of the initially homogeneous microstructure into two distinct phases: the W-rich phase (αW, Cr) and the Cr-rich phase (αCr, W). Cr-rich phases preferentially form at grain boundaries, where yttrium oxides are also located, and gradually coarsen to the submicron range with increasing annealing time. The chemical compositions of both phases remain relatively stable after 75 h of annealing. The Cr content in (αW, Cr) is 18.6 at.% at 75 h and 17.8 at.% at 100 h. Compared to the as-sintered state, the 100 h-annealed material exhibits significant softening at room temperature and demonstrates increased flexural strength across all tested temperatures, but lower fracture toughness at elevated temperatures. The oxidation behavior of the 100 h-annealed material under humid air at 1000 °C reveals two stages in its TGA curve: inital growth of the inner oxide layer followed by subsequent development of the protecting chromia layer. In contrast, the as-sintered material exhibits a continuous, linear mass increase throughout the oxidation process. These findings present promising prospects of the decomposed microstructure for first wall applications.
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来源期刊
Nuclear Materials and Energy
Nuclear Materials and Energy Materials Science-Materials Science (miscellaneous)
CiteScore
3.70
自引率
15.40%
发文量
175
审稿时长
20 weeks
期刊介绍: The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.
期刊最新文献
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