Surface modification of alloys to reduce Hydrogen permeability in fusion alloys

合金表面改性以降低熔合合金的氢渗透率

• 批准号: 2889391
• 金额: --
• 依托单位: University of Liverpool
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2023
• 资助国家: 英国
• 起止时间: 2023 至 无数据
• 项目状态: 未结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2889391
• 关键词: Surface; modification; alloys; reduce; Hydrogen

It is imperative to reduce the loss of Tritium to provide safe and sustainable fusion energy. Hence, preventing accumulation and permeation of Tritium in reactor walls is critical. The purpose of this project is to understand Hydrogen (H), Deuterium (D) and Tritium (T) permeation in current fusion alloys and the influence of microstructural features/surface modifications to provide as barrier. It is well known that different alloys and metals have drastically different permeabilities and while these are quite high for Austenitic steels and Tungsten, the materials themselves also need to serve as structural materials while withstanding radiation damage at high temperatures. While several options of barrier coatings have been considered for reduced activation steels and tungsten, the influence of complex interfaces and near surface modifications has not been investigated on an atomic scale.The project plans to explore and perform surface modification of Eurofer and Tungsten using traditional and advanced methods and subsequent heat treatment to tailor material features (e.g.defects, grain boundaries and precipitates) in the first 10 -30 microns of these materials. Techniques like Thermal Desorption Spectroscopy (TDS), Nano-SIMS and Nuclear Reaction Analysis (NRA) and Heavy Ion Elastic Recoil Detection Analysis (HE-ERDA) will also be used to deduce the binding energies of various material features and to quantify the depth profile of H/D/T. In-situ TEM in hydrogen atmosphere will also be used to understand at atomic level, interaction of H with tailored material features.The experiment will utilise the UKAEA's Hydrogen-3 Advanced Technology (H3AT) infrastructure to expose materials samples to hydrogen isotopes using DELPHI (Device for Exposure to Low-energy Plasma of Hydrogen Isotopes). Primarily H and D will be used as a substitute for T, however the UKAEAs TDS and DELPHI systems are tritium compatible

必须减少trif的损失，以提供安全可持续的融合能。因此，防止反应堆壁中的tri骨积聚和渗透至关重要。该项目的目的是了解当前融合合金中的氢（H），氘（D）和Tritium（t）渗透，以及微结构特征/表面修饰的影响以作为屏障提供。众所周知，不同的合金和金属具有截然不同的渗透率，尽管对于奥氏体钢和钨而言，这些合金和金属的渗透率很高，但这些材料本身也需要用作结构材料，同时在高温下承受辐射损害。 While several options of barrier coatings have been considered for reduced activation steels and tungsten, the influence of complex interfaces and near surface modifications has not been investigated on an atomic scale.The project plans to explore and perform surface modification of Eurofer and Tungsten using traditional and advanced methods and subsequent heat treatment to tailor material features (e.g.defects, grain boundaries and precipitates) in the first 10 -30 microns of these materials.诸如热解吸光谱（TDS），纳米SIMS和核反应分析（NRA）以及重离子弹性后坐力检测分析（HE-ERDA）等技术也将用于推断各种材料特征的结合能并量化H/D/T的深度谱。氢气中的原位TEM也将用于在原子水平上理解，H与量身定制的材料特征的相互作用。实验将利用UKAEA的氢-3先进技术（H3AT）基础架构将材料样品暴露于使用Delphi的氢（用于暴露于低Enerergy Qualergy Qualergy Qualyergy Qualygopma of Hydrogoposes的设备）。 H和D主要将用作T的替代品，但是Ukaeas TD和Delphi系统兼容