空位、自间隙原子和嬗变铼对钨晶格热导率的影响

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Daigo Kanamori , Keisuke Mukai , Takeo Hoshi , Takuya Nagasaka
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引用次数: 0

摘要

钨(W)由于其优异的性能,如高熔点和高导热性(TC),是一种很有前途的等离子体表面元件(pfc)的候选者。然而,中子辐照引入晶格缺陷和嬗变,导致材料性能下降。在本研究中,利用平衡分子动力学(EMD)计算了W中空位、自间隙原子、取代铼(Re)和间隙Re等点缺陷引起的晶格热导率(LTC)的降低。此外,我们计算了声子态密度(DOS),并讨论了点缺陷如何改变w晶体的声子态密度。结果发现,间隙Re对LTC的降低最为显著,其次是随机自间隙原子、空位和取代Re。此外,EMD计算声子-声子散射率的结果与从头算方法的计算结果存在明显偏差。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effect of vacancy, self-interstitial atoms and transmutation rhenium on lattice thermal conductivity in tungsten
Tungsten (W) is a promising candidate for plasma-facing components (PFCs) because of its excellent properties, such as a high melting point and high thermal conductivity (TC). However, neutron irradiation introduces lattice defects and transmutation, leading to the degradation of material properties. In this study, the reduction of lattice thermal conductivity (LTC) in W caused by point defects, such as vacancies, self-interstitial atoms, substitutional rhenium (Re) and interstitial Re were calculated using molecular dynamics at 300 K and 800 K using equilibrium molecular dynamics (EMD). Also, we calculate phonon density of state (DOS) and discuss how the point defects change the phonon DOS of crystalline W. It was found that interstitial Re decreased LTC most significantly, followed by random self-interstitial atoms, vacancies, and substitutional Re. Additionally, it was found that the calculation results of the phonon-phonon scattering rate by EMD deviate significantly from those by the ab initio method.
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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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