基于第一性原理计算的W-Fe梯度界面的粘附性能和损伤容限

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Liang Chen , Qian Wang , Chaoping Liang
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引用次数: 0

摘要

在钨与钢结合的实验中,已经开发出了成分和结构梯度变化的过渡多层材料,但对层数和成分的设计研究较少。在这项工作中,采用第一性原理计算和热力学建模相结合的方法,深入研究了层数和成分对富w和富fe W-Fe双层材料的粘附强度、界面稳定性、断裂韧性和损伤容限的影响。研究发现,在富w区中保留更多的分级层可以保持界面附着力,提高损伤容限,富w区的设计应重点考虑Fe5W3//Fe6W2和Fe6W2//Fe8的特定双层结构。所得结果与实验结果吻合较好,为本文提出的梯度多层材料的性能提供了深入的机理理解。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Adhesion properties and damage tolerance of W-Fe graded interfaces from first-principles calculation
Transitional multilayers with a gradient change of compositions and structures have been developed for the bonding between tungsten and steel in the experiments, however, very few works have focused on the design of the layer amount and composition. In this work, the influences of layer amount and composition on adhesion strength, interface stability, fracture toughness, and damage tolerance of W-rich and Fe-rich W-Fe bilayers were thoroughly examined using a combination of first-principles calculations and thermodynamic modeling. It is found that keeping more graded layers of W-rich region can maintain interface adhesion and improve damage tolerance, and the specific bilayers of Fe5W3//Fe6W2 and Fe6W2//Fe8 should be chiefly considered in the design of Fe-rich region. The derived results are in good agreement with the experimental observations, and provide a deep mechanistic understanding of the performances of the graded multilayers proposed in the present work.
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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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