Results 111 to 120 of about 898 (196)

Influence of Stabilizing Elements on Ductile-Brittle Transition Temperature (DBTT) of 18Cr Ferritic Stainless Steels

open access: yesISIJ International, 2022
Yoshino, Masataka   +3 more
openaire   +2 more sources

Radiation damage in tungsten under high-energy He-ion irradiation

open access: yesCommunications Materials
Tungsten (W) is a primary candidate for plasma-facing components (PFCs) in fusion reactors and hybrid fission-fusion reactors. However, W suffers from severe microstructural damage under Helium (He) ion irradiation in operation conditions.
Yinghang Liu   +10 more
doaj   +1 more source

The Effect of Phosphorus on Low-Temperature Brittleness in the Coarse-Grained Heat-Affected Zone of P-SA508-4N RPV Steel

open access: yes
The coarse-grained heat-affected zone (CGHAZ) is a critical brittle region in welded reactor pressure vessel steels, and phosphorus segregation at prior-austenite grain boundaries can further impair its low-temperature toughness during long-term service.
Yu Guo   +5 more
core   +1 more source

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