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UKAEA-CCFE-PR(22)322022
Vanadium base alloys represent potentially promising candidate structural materials for use in nuclear fusion reactors due to vanadium’s low activity, high thermal strength, and good swelling resistance. In this work, the mechanical properties of the current frontrunner vanadium base alloy, V-4Cr-4Ti, have been interrogated using in-situ high ene…
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UKAEA-CCFE-CP(23)212021
Sandwich-type cooling pipes of the first wall of future fusion nuclear reactors (i.e. DEMO) will likely consist of tungsten brazed to a Reduced Activation Ferritic Martensitic (RAFM) steel. Under a high heat flux (HHF) (1-5 MW/m2) the mismatch in thermal expansion between tungsten and steel results in significant thermal stresses in the brazing …
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UKAEA-CCFE-PR(21)752021
Eurofer97 steel is a primary structural material for the plasma facing-components of future fusion reactors. Laser welding is a promising technique that can overcome the challenges of remote handling and maintenance. However, the interaction of the induced residual stress distribution with the heterogeneous microstructure may degrade the mechanical…
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UKAEA-CCFE-PR(21)592021
The plasma-facing components of future fusion reactors, where the Eurofer97 is the primary structural material, will be assembled by laser-welding techniques. The heterogeneous residual stress induced by welding can interact with the microstructure, resulting in a degradation of mechanical properties and a reduction in joint lifetime. Here, a Xe
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UKAEA-CCFE-CP(21)042021
The use of small specimen test techniques (SSTT) to determine mechanical properties of irradiated materials has been studied over the previous decades both in fission and fusion programs, but also to characterise and optimise new materials by nuclear and non-nuclear communities. Currently a number of activities are running that focus on the standar…
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UKAEA-CCFE-PR(20)1262020
Martensitic stainless steels have been widely used in industries due to their high strength and good corrosion resistance performance. Precipitation-hardened (PH) martensitic stainless steels are featured by their very high strength compared with other stainless steels, around 3-4 times of the strength of austenitic stainless steels such as 304 and…
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UKAEA-CCFE-PR(20)842020
Precipitation hardened Copper-Chromium-Zirconium (CuCrZr) alloy is a prime candidate for divertor components in future European DEMOnstration fusion reactors. To develop the DEMO Design Criteria for In-vessel Components (DDC-IC), the failure criterion of CuCrZr needs to be investigated. Hence, the effects of stress triaxiality and loading…
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UKAEA-CCFE-PR(20)142020
Crystal plasticity finite element (CPFE) modelling is an effective tool from which detailed information on the meso-scale behaviour of crystalline metallic systems can be extracted and used, not only to enhance the understanding of material behaviour under different loading conditions, but also to improve the structural integrity assessment of e…
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UKAEA-CCFE-PR(19)802019
Deformation mechanisms of high entropy alloys (HEAs) at cryogenic temperatures have attracted extensive research interest. We used in situ neutron diffraction to study the tensile behavior of a face-centered- cubic HEA at 77 and 15 K and compared its stacking fault energy (SFE) at ambient and cryogenic temperatures. The SFE dropped from 28 mJm −2…
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UKAEA-CCFE-PR(19)712019
Deformation mechanisms of high entropy alloys (HEAs) at cryogenic temperatures have attracted extensive research interest. We used in situ neutron diffraction to study the tensile behavior of a face-centered-cubic HEA at 77 and 15 K and compared its stacking fault energy (SFE) at ambient and cryogenic temperatures. The SFE dropped from 28…
Showing 11 - 20 of 23 UKAEA Paper Results