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Tungsten (W) is the leading candidate material for plasma-facing components in fusion reactors, yet its upper operational temperature is limited by premature grain growth and recrystallization processes. Irradiation adds further…

材料科学 · 物理学 2026-02-23 Jinxin Yu , Sicong He , Giacomo Po , Jason R. Trelewicz , Timothy J. Rupert , Jaime Marian

Due to their high strength and advantageous high-temperature properties, tungsten-based alloys are being considered as plasma-facing candidate materials in fusion devices. Under neutron irradiation, rhenium, which is produced by nuclear…

材料科学 · 物理学 2016-08-03 Leili Gharaee , Jaime Marian , Paul Erhart

Refractory High-Entropy Alloys (RHEAs) hold promising potential to be used as structural materials in future nuclear fusion reactors, where W and its alloys are currently leading candidates. Fusion materials must be able to withstand…

Developing materials that can withstand the intense environments of nuclear fusion reactors is critical in developing long-term commercial viability for energy production. Tungsten is the primary candidate as a plasma facing material due to…

材料科学 · 物理学 2023-12-11 Jarod Worden , Celine Hin

In the quest of new materials that can withstand severe irradiation and mechanical extremes for advanced applications (e.g. fission reactors, fusion devices, space applications, etc), design, prediction and control of advanced materials…

The production of energy through nuclear fusion poses serious challenges related to the stability and performance of materials in extreme conditions. In particular, the constant bombardment of the walls of the reactor with high doses of He…

材料科学 · 物理学 2015-03-06 Danny Perez , Thomas Vogel , Blas P. Uberuaga

High-temperature, high-dose, neutron irradiation of W results in the formation of Re-rich clusters at concentrations one order of magnitude lower than the thermodynamic solubility limit. These clusters may eventually transform into brittle…

材料科学 · 物理学 2021-01-14 Chen-Hsi Huang , Leili Gharaee , Yue Zhao , Paul Erhart , Jaime Marian

Newest developments in nuclear fission and fusion technology as well as planned long-distance space missions demand novel materials to withstand harsh, irradiative environments. Radiation-induced hardening and embrittlement are a concern…

Tungsten (W) is a material of choice for the divertor material due to its high melting temperature, thermal conductivity, and sputtering threshold. However, W has a very high brittle-to-ductile transition temperature and at fusion reactor…

材料科学 · 物理学 2023-03-29 E. L. Sikorski , M. A. Cusentino , M. J. McCarthy , J. Tranchida , M. A. Wood , A. P. Thompson

A novel W-based refractory high entropy alloy with outstanding radiation resistance has been developed. The alloy was grown as thin films showing a bimodal grain size distribution in the nanocrystalline and ultrafine regimes and a unique 4…

Predicting the dramatic changes in material properties caused by irradiation damage is key for the design of future nuclear fission and fusion reactors. Self-ion implantation is an attractive tool for mimicking the effects of neutron…

计算物理 · 物理学 2020-08-26 Suchandrima Das , Hongbing Yu , Kenichiro Mizohata , Edmund Tarleton , Felix Hofmann

High-entropy alloys (HEAs) based on tungsten (W) have emerged as promising candidates for plasma-facing components in future fusion reactors, owing to their excellent irradiation resistance. In this study, we construct an efficient…

材料科学 · 物理学 2025-07-17 Jiahui Liu , Jesper Byggmastar , Zheyong Fan , Bing Bai , Ping Qian , Yanjing Su

Hydrogen isotopes are retained in materials for fusion power applications, changing both hydrogen embrittlement and tritium inventory as the microstructure undergoes irradiation damage. But modelling of highly damaged materials - exposed to…

Plasma-facing materials (PFMs) represent one of the most significant challenges for the design of future nuclear fusion reactors. Inside the reactor, the divertor will experience the harshest material environment: intense bombardment of…

材料科学 · 物理学 2024-07-02 Andrea Fedrigucci , Nicola Marzari , Paolo Ricci

Tungsten-based low-activation high-entropy alloys are possible candidates for next-generation fusion reactors due to their exceptional tolerance to irradiation, thermal loads, and stress. We develop an accurate and efficient machine-learned…

Magnetic materials for specific applications require an accurate control and complete comprehension of their magnetic properties. In particular, nanoparticles embedded in a polycrystalline matrix emerge as good candidates for applications…

Alloying elements play an important role in the design of plasma facing materials with good comprehensive properties. Based on first-principles calculations, the stability of alloying element W and its interaction with vacancy defects in…

材料科学 · 物理学 2019-11-01 Yini Lv , Kaige Hu , Shulong Wen , Min Pan , Zheng Huang , Zelin Cao , Yong Zhao

Tungsten is the main candidate material for plasma-facing armour components in future fusion reactors. In-service, fusion neutron irradiation creates lattice defects through collision cascades. Helium, injected from plasma, aggravates…

材料科学 · 物理学 2020-08-26 Suchandrima Das , Hongbing Yu , Edmund Tarleton , Felix Hofmann

The combinatorial approach to all oxide material and device research is based on the synthesis of hundreds of related materials in a single experiment. This approach requires the development of new tools to rapidly characterize these…

化学物理 · 物理学 2015-08-20 Klimentiy Shimanovich

Radiation damage in high-temperature cuprate superconductors represents one of the main technological challenges for their deployment in harsh environments, such as fusion reactors and accelerator facilities. Their complex crystal structure…

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