Results 101 to 110 of about 3,792 (227)

Effects of long-term aging on ductility of the columbium alloys C-103, Cb-1Zr, and Cb-752 and the molybdenum alloy Mo-TZM [PDF]

open access: yes
A program was conducted to determine if aging embrittlement occurs in the columbium alloys C-103, CB-1Zr, and Cb-752 or in the molybdenum alloy Mo-TZM.
Stephens, J. R.
core   +1 more source

Direct prediction of the solute softening-to-hardening transition in W-Re alloys using stochastic simulations of screw dislocation motion

open access: yes, 2017
Interactions among dislocations and solute atoms are the basis of several important processes in metals plasticity. In body-centered cubic (bcc) metals and alloys, low-temperature plastic flow is controlled by screw dislocation glide, which is known to ...
Marian, Jaime, Zhao, Yue
core   +2 more sources

Exploratory study of silicide, aluminide, and boride coatings for nitridation-oxidation protection of chromium alloys [PDF]

open access: yes
Protective coatings for chromium alloys for use in advanced air breathing ...
Klopp, W. D., Stephens, J. R.
core   +1 more source

Influence of Inclusions on the Mechanical Properties of RAFM Steels Via Y and Ti Addition

open access: yesMetals, 2019
The effects of the Y- and Ti-containing inclusions on the tensile and impact properties of reduced activation ferritic martensitic (RAFM) steels were evaluated. Four steels with different Y and Ti contents were produced via vacuum induction melting.
Guoxing Qiu   +6 more
doaj   +1 more source

Effects of additions of nonmetallics on the properties of vapor-deposited tungsten [PDF]

open access: yes
Nonmetallic additive effects on properties of vapor deposited ...
Chin, J.   +2 more
core   +1 more source

Development of innovative materials and thermal treatments for DEMO water cooled blanket

open access: yesNuclear Materials and Energy, 2019
One of the options currently taken into account for the realization of the first DEMO reactor is the “water-cooled lanket”. This option implies an irradiation temperature for the blanket material in the range of 280–350 °C.
L. Pilloni   +5 more
doaj   +1 more source

Effects of Y and Ti addition on microstructure stability and tensile properties of reduced activation ferritic/martensitic steel

open access: yesNuclear Engineering and Technology, 2019
The effects of Y and Ti on the microstructure stability and tensile properties of the reduced activation ferritic/martensitic steel have been investigated.
Guoxing Qiu   +5 more
doaj   +1 more source

Development of a chromium-thoria alloy [PDF]

open access: yes
Low temperature ductility and high temperature strength of pure chromium and chromium-thoria alloy prepared from vapor deposited ...
Blocher, J. M., Jr.   +7 more
core   +1 more source

Fabrication techniques developed for small- diameter, thin-wall tungsten and tungsten alloy tubing [PDF]

open access: yes, 1968
Report describes methods for the fabrication of tungsten and tungsten alloys into small-diameter, thin-wall tubing of nuclear quality. The tungsten, or tungsten alloy tube blanks are produced by double extrusion.
Brillhart, D. C.   +3 more
core   +1 more source

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