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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-PR(21)572021
Small punch testing was carried out on Copper-Chromium-Zirconium alloy subjected to two heat treatment conditions –both quenched and one subjected to subsequent aging. The variation in the load displacement characteristics associated with the testing was attributed to differences in plastic and damage properties evolved as a consequence of these …
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UKAEA-CCFE-PR(21)122021
Small punch creep (SPC) testing represents an effective way to rapidly assess the creep performance of novel materials and potentially monitor degradation of in-service components. Recent progress in standardisation has also led to improvements in data analysis. However, estimation of equivalent uniaxial stresses is still somewhat challenging and h…
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UKAEA-CCFE-PR(21)062020
This work addresses an overview of the recent progress, associated risks and development plans of structural materials for in-vessel components (IVCs) in DEMO plants. Reduced Activation Ferritic Martensitic Steels form the primary structural materials for most DEMOs IVCs and will be the focus of the paper. An overview of EU- and J-DEMO…
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UKAEA-CCFE-CP(20)1172020
The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reac…
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UKAEA-CCFE-PR(20)1122020
A technology readiness assessment has been carried out on materials under development within the EUROfusion materials work package (WPMAT). This covers materials for structural, high heat flux and functional applications (breeder materials and coatings are not covered). The baseline materials have been assigned Material Technology Readiness Levels …
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UKAEA-CCFE-PR(20)1072020
One of the key challenges for the development of high-performance fusion materials is to design materials capable of maintaining mechanical and structural integrity under the extreme levels of displacement damage, high temperature and transmutation rates. High-entropy alloys (HEAs) and other concentrated alloys have attracted attention with rega…
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UKAEA-CCFE-PR(20)972020
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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…
Showing 11 - 20 of 36 UKAEA Paper Results