Behavior of tungsten under irradiation and plasma interaction

M Rieth, R Doerner, A Hasegawa, Y Ueda… - Journal of Nuclear …, 2019 - Elsevier
In 1959 the Journal of Nuclear Materials (JNM) was founded and is now celebrating its
Diamond Anniversary year. The present paper is part of a series in which single JNM …

A review of late-stage tungsten fuzz growth

JAR Wright - Tungsten, 2022 - Springer
Tungsten will be used as the plasma-facing divertor material in the International
Thermonuclear Experimental Reactor (ITER) fusion reactor. Under high temperatures and …

Grain boundary softening from stress assisted helium cavity coalescence in ultrafine-grained tungsten

WS Cunningham, Y Zhang, SL Thomas, O El-Atwani… - Acta Materialia, 2023 - Elsevier
The formation of helium cavities in coarse-grained materials produces hardening
proportional to the number density and size of the cavities and due to the interaction of …

Effects of transition metal carbide dispersoids on helium bubble formation in dispersion-strengthened tungsten

A Saefan, X Liu, E Lang, L Higgins, Y Wang… - Scientific reports, 2023 - nature.com
The formation of helium bubbles and subsequent property degradation poses a significant
challenge to tungsten as a plasma-facing material in future long-pulse plasma-burning …

[HTML][HTML] Tungsten fuzz: Deposition effects and influence to fusion devices

S Kajita, N Yoshida, N Ohno - Nuclear Materials and Energy, 2020 - Elsevier
Helium (He) plasma irradiation to tungsten leads to formation of He bubbles and fiberform
nanostructures called fuzz on the surface. Although the fuzz growth condition and growth …

A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten

YG Li, QR Zheng, LM Wei, CG Zhang, Z Zeng - Tungsten, 2020 - Springer
The change in surface damage/microstructures and its effects on the hydrogen (H)
isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten …

Recent progress on preparation routes and performance evaluation of ODS/CDS-W alloys for plasma facing materials in fusion devices

LM Luo, ZH Zhao, G Yao, YC Wu - Journal of Nuclear Materials, 2021 - Elsevier
Tungsten (W) is considered as an ideal candidate matrix metal for plasma-facing materials
(PFMs) in a fusion reactor owing to its high melting point and elastic modulus, high thermal …

Enhanced radiation resistance of W-based HEA under helium-ion irradiation conditions

K Wang, Y Yan, Y Xiong, S Zhao, D Chen… - Journal of Nuclear …, 2024 - Elsevier
Recently, high entropy alloy (HEA) has demonstrated superior radiation resistance to
energetic particles. In this paper, we examine the radiation response of W-based HEA …

Theoretical model of helium bubble growth and density in plasma-facing metals

KD Hammond, D Maroudas, BD Wirth - Scientific Reports, 2020 - nature.com
We present a theoretically-motivated model of helium bubble density as a function of volume
for high-pressure helium bubbles in plasma-facing tungsten. The model is a good match to …

Continuum-scale modeling of helium bubble bursting under plasma-exposed tungsten surfaces

S Blondel, DE Bernholdt, KD Hammond… - Nuclear Fusion, 2018 - iopscience.iop.org
We present a comparison between a continuum-scale drift-diffusion-reaction cluster
dynamics prediction of helium retention in low-energy helium plasma exposed tungsten and …