SS-316L 表面 Al2O3/Fe-Al 层的形成、表征和氘渗透

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2024-11-16 DOI:10.1016/j.fusengdes.2024.114735

Feilong Yang, Xin Xiang, Chang'an Chen, Li Hu, Ce Ma, Guikai Zhang, Yaqi Song

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引用次数: 0

摘要

316L 奥氏体不锈钢（SS-316L）是聚变反应堆中最有前途的氚候选结构材料。然而，SS-316L 在高温下的氚渗透会导致氚的损失，最终产生放射性危害并挑战氚的自给自足。在 SS-316L 表面制备氚渗透屏障（TPB）是解决这一问题的关键途径。在这项研究中，通过 "镀铝+氧化 "工艺将 Al2O3/Fe-Al 涂层应用于 SS-316L 表面，然后对其微观结构及其抗氚性能进行了详细分析。结果表明，制备的涂层结构由 10 微米厚的铁铝过渡层和 100 纳米厚的致密 Al2O3 膜组成。该涂层的抗氘性排名靠前，在 500 °C 时氘渗透率可降低三个数量级。

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Formation, characterization and deuterium permeation of Al2O3/Fe-Al layers on SS-316L surface

316L austenitic stainless steel (SS-316L) is the most promising candidate structural material facing tritium in fusion reactors. However, tritium permeation of SS-316L at high temperatures will lead to loss of tritium, which ultimately generates radiological hazards and challenges tritium self-sufficiency. Preparing tritium permeation barriers (TPBs) on SS-316L surfaces is a critical way to solve this problem. In this study, Al₂O₃/Fe-Al coatings were applied to the SS-316L surface through an "aluminizing + oxidation" process, followed by a detailed analysis of the microstructures and their deuterium-resistant properties. Results delivered that the prepared coating structure comprises a 10-micron-thick Fe-Al transition layer and a dense hundred-nanometer-thick Al₂O₃ film. The deuterium resistance of the coating is ranking, where the deuterium permeability can be reduced by three orders of magnitude at 500 °C.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.