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 …

Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan

S Nogami, A Hasegawa, M Fukuda, M Rieth… - Journal of Nuclear …, 2021 - Elsevier
There remain some drawbacks of mechanical properties of W materials as a plasma facing
material (PFM) for fusion reactor divertors, which are low temperature brittleness, high …

Tungsten modified by potassium doping and rhenium addition for fusion reactor applications

S Nogami, A Hasegawa, M Fukuda, S Watanabe… - Fusion Engineering and …, 2020 - Elsevier
Low temperature brittleness, high ductile-to-brittle transition temperature (DBTT), and
recrystallization-induced embrittlement are potential drawbacks related to the thermo …

[HTML][HTML] Brittle-ductile transition temperature of recrystallized tungsten following exposure to fusion relevant cyclic high heat load

V Shah, JAW van Dommelen, E Altstadt, A Das… - Journal of Nuclear …, 2020 - Elsevier
The lifetime of tungsten (W) monoblocks under fusion conditions is ambivalent. In this work,
the microstructure dependent mechanical behaviour of pulsed high heat flux (HHF) exposed …

Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures

T Miyazawa, LM Garrison, JW Geringer… - Journal of Nuclear …, 2020 - Elsevier
The tensile properties of powder-metallurgical-processed Pure W, K-doped W, W-3% Re,
and K-doped W-3% Re were examined after neutron irradiation up to 0.7 dpa at 910–1020° …

[HTML][HTML] Helium effects on tensile properties of powder metallurgical-processed tungsten for fusion reactor applications

A Hasegawa, Y Sato, T Hattori, R Kanamaru… - Nuclear Materials and …, 2021 - Elsevier
Powder metallurgical processing of Tungsten (W) followed by thermomechanical treatment,
including rolling and stress relief (SR) heat treatment, is a candidate fabrication process for …

Influence of recrystallization on tungsten divertor monoblock under high heat flux

YZ Jin, X Liu, YY Lian, JP Song - Tungsten, 2022 - Springer
Extremely high heat flux reaching 20 MW· m− 2 can be foreseen for the future fusion reactor.
Such high heat flux would induce recrystallization of tungsten (W) material, leading to …

[HTML][HTML] Experimental investigation of the microstructural changes of tungsten monoblocks exposed to pulsed high heat loads

V Shah, M van Maris, JAW van Dommelen… - Nuclear Materials and …, 2020 - Elsevier
Extending the lifetime of tungsten based plasma facing components for future fusion reactors
remains an everlasting challenge. In this work, the microstructure of tungsten monoblocks …

[HTML][HTML] Impact of creep-fatigue interaction on divertor tungsten under high heat flux

YZ Jin, H Wang, X Liu, YY Lian, F Feng, J Wang… - Nuclear Materials and …, 2023 - Elsevier
High heat flux as 20 MW m− 2 during stationary operation can be foreseen in future fusion
devices, leading to recrystallization and thermal creep in tungsten targets. Both …

High heat flux testing of newly developed tungsten components for WEST

G Pintsuk, M Missirlian, GN Luo, Q Li, W Wang… - Fusion Engineering and …, 2021 - Elsevier
In preparation of the production of the actively cooled tungsten targets for the lower divertor
of WEST (W-for tungsten-Environment in Steady-state Tokamak), the qualification of …