Restoration in drawn tungsten wires of tungsten fiber-reinforced tungsten composites

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Daniel Ahlin Heikkinen Wartacz , Johann Riesch , Karen Pantleon , Wolfgang Pantleon
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Abstract

Fusion energy holds great promise as a sustainable solution to meet global energy demands, offering a quasi-inexhaustible, secure and environmentally friendly energy resource. Materials facing the burning plasma in fusion reactors must withstand extreme conditions. Tungsten, the current choice for plasma-facing materials, is at risk of embrittlement if exposed to high temperatures due to restoration processes increasing its ductile-to-brittle transition temperature. This embrittlement limits operation of tungsten under fusion-relevant conditions. Tungsten fiber-reinforced tungsten (Wf/W) composites are developed to mitigate brittleness and achieve pseudo-ductile behavior, utilizing drawn, potassium-doped tungsten fibers embedded in a pure tungsten matrix to enhance toughness compared to pure tungsten significantly. In view of the high heat fluxes and the expected high steady-state operation temperatures in a fusion reactor, thermal stability of the plasma-facing material becomes crucial. Model Wf/W systems containing a single tungsten fiber in a dense tungsten matrix, with or without an yttria interlayer, are annealed at 1450 °C for up to 2 days to evaluate their thermal stability. As the tungsten fibers are primarily responsible for the pseudo-ductile behavior, this investigation focuses on analyzing the thermal stability of the fibers and their immediate vicinity in the surrounding matrix. Changes within the tungsten fibers, including alterations of boundary spacing and crystallographic texture, are analyzed using electron backscatter diffraction (EBSD) and further post-processing of the orientation data. Quantification shows a substantial increase in boundary spacing in the fibers after annealing. This indicates recrystallization, where many boundaries with disorientation angles up to 50°are removed. The crystallographic texture in the fibers changes only slightly during annealing, if at all.
钨纤维增强钨复合材料拉丝的修复
作为满足全球能源需求的可持续解决方案,核聚变能源具有巨大的前景,它提供了一种近乎取之不尽、安全、环保的能源资源。在聚变反应堆中,面对燃烧等离子体的材料必须能承受极端条件。钨是目前等离子体表面材料的选择,如果暴露在高温下,由于恢复过程会增加其韧脆转变温度,因此有脆化的风险。这种脆化限制了钨在熔化相关条件下的操作。钨纤维增强钨(Wf/W)复合材料的开发是为了减轻脆性和实现伪延性,利用拉伸的、掺钾的钨纤维嵌入纯钨基体中,与纯钨相比,显著提高韧性。鉴于聚变反应堆的高热流密度和预期的高稳态工作温度,等离子体材料的热稳定性变得至关重要。模型Wf/W系统包含一个钨纤维在密集的钨基体,有或没有钇中间层,在1450°C退火长达2天,以评估其热稳定性。由于钨纤维主要负责伪延性行为,本研究的重点是分析纤维及其在周围基体中的邻近区域的热稳定性。利用电子背散射衍射(EBSD)和进一步后处理的取向数据分析了钨纤维内部的变化,包括边界间距和晶体织构的变化。定量分析表明,退火后纤维的边界间距显著增加。这表明再结晶,其中许多失向角高达50°的边界被移除。在退火过程中,纤维的晶体结构即使有变化,也只有轻微的变化。
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来源期刊
Fusion Engineering and Design
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.
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