Results 101 to 110 of about 867 (170)

Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels [PDF]

open access: yes, 1997
Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 12Cr-1MoVW (Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C) steels have been considered potential structural materials for future fusion power plants.
Klueh, R.L., Alexander, D.J.
core  

Master of Science

open access: yes, 2018
thesisThe relationship between the grain size and mechanical properties of tungsten alloys was studied for potential improvement in ductility through minimization of grain size and for possible modification to the ductile-to-brittle transition ...
Zhang, Huan
core  

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

Competing mechanisms toughen bcc binary and medium-entropy alloys at 20 K. [PDF]

open access: yesNature
Cook DH   +16 more
europepmc   +1 more source

Strength, ductility, and ductile-brittle transition temperature for MFR (magnetic fusion reactor) candidate vanadium alloys

open access: yes, 1987
The dependence of the yield strength, tensile strength, elongation, and reduction in area on temperature for the V-15Ti-7.5Cr, V-20Ti, V-15Cr-5Ti, V-12Cr-5Ti, V-10Cr-5Ti, and V-3Ti-1Si alloys was determined from tensile tests at temperatures ranging from
Lee, R. H.   +3 more
core  

Home - About - Disclaimer - Privacy