Tay Sparks Duc Nguyen-Manh Pengfei Zheng Jan S. Wróbel Michael Gorley Thomas Connolley Christina Reinhard Yiqiang Wang Biao Cai
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…
Preprint PurchaseGerald Pintsuk Giaocomo Aiello Sergei L. Dudarev Michael Gorley Jean Henry Marianne Richou Michael Rieth D. Terentyev Rafael Vila
The EUROfusion materials research program for DEMO in-vessel components aligns with the European Fusion Roadmap and comprises the characterization and qualification of the in-vessel baseline materials EUROFER97, CuCrZr and tungsten, advanced structural and high heat flux materials developed for risk mitigation, as well as optical and dielectric fun…
Preprint PublishedD.J.M. King A.J. Knowles D. Bowden M.R. Wenman S. Capp M. Gorley J. Shimwell L. Packer M.R. Gilbert A. Harte
This Review considers current Zr alloys and opportunities for advanced zirconium alloys to meet the demands of a structural material in fusion reactors. Zr based materials in the breeder blanket offer the potential to increase the tritium breeding ratio above that of Fe, Si and V based materials. Current commercial Zr alloys might be considered …
Preprint PublishedBin Zhu Nathanael Leung Winfried Kockelmann Saurabh Kabra Andrew J. London Michael Gorley Mark J. Whiting Yiqiang Wang Tan Sui
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…
Preprint PurchaseBin Zhu Yiqiang Wang Jiří Dluhoš Andy J. London Michael Gorley Mark J. Whiting Tan Sui
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
Preprint PublishedV.D. Vijayananda M. Mokhtarishirazabad Y. Wang M. Gorley D.M. Knowles M. Mostafavi
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 …
PreprintM. Richardson M. Gorley Y. Wang D. Andres H. Dawson
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…
Preprint PublishedM. Gorley G. Aiello J. Henry T. Nozawa G. Pintsuk M. Rieth H. Tanigawa
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…
Preprint PublishedT.L. Martin A.D. Warren D. Kumar A. Siberry R. Springell R. Holmes R. Clark L. Platts R. Burrows C. Harrington M. Gorley E. Surrey S. Rowthu P. Grundler S. Ritter
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…
PreprintM. D. Richardson M. Gorley Y. Wang G. Aiello G. Pintsuk E. Gaganidze M. Richou J. Henry R. Vila M. Rieth
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 …
Preprint Published