Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels [PDF]
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.
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Effect of Delamination and Grain Refinement on Fracture Energy of Ultrafine-Grained Steel Determined Using an Instrumented Charpy Impact Test. [PDF]
Inoue T, Kimura Y.
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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
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Radiation damage in tungsten under high-energy He-ion irradiation
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
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Influence of Martensite/Bainite Dual Phase-Content on the Mechanical Properties of EA4T High-Speed Axle Steel. [PDF]
Zhang Y +5 more
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Relative mobility of screw versus edge dislocations controls the ductile-to-brittle transition in metals. [PDF]
Lu Y, Zhang YH, Ma E, Han WZ.
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Analysis of Magnetic Nondestructive Measurement Methods for Determination of the Degradation of Reactor Pressure Vessel Steel. [PDF]
Vértesy G +5 more
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Elucidating the Effect of Step Cooling Heat Treatment on the Properties of 2.25 Cr-1.0 Mo Steel Welded with a Combination of GMAW Techniques Incorporating Metal-Cored Wires. [PDF]
Das S +5 more
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Competing mechanisms toughen bcc binary and medium-entropy alloys at 20 K. [PDF]
Cook DH +16 more
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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
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