Qiong Lu1 Chi Zhang Wei Wang Shuai Jiang Lee Aucott Jun Jiang
Stainless-steel 316L is one of the widely used structural materials in the nuclear industry, because of its excellent corrosion resistance and mechanical properties. However, very few researches can be found on its viscoplastic behavior and microstructure evolution at warm and hot deformation conditions, which hinder the possible applicat…
Preprint PublishedO. El Atwani H.T. Vo M. Tunes C. Lee A. Alvarado N. Krienke J. Poplawsky A.A. Kohnert J. Gigax W.-Y. Chen M. Li Y. Wang J.S. Wróbel Duc Nguyen-Manh J.K.S. Baldwin U. Tukac E. Aydogan S. Fensin E. Martinez
In the quest of new materials that can withstand severe irradiation and mechanical extremes for advanced applications (e.g. fission reactors, fusion devices, space applications, etc), design, prediction and control of advanced materials beyond current material designs become a paramount goal. Here, though a combined experimental and simula…
PreprintLei Tang Fuqing Jian Yiqiang Wang Saurabh Kabra Biao Cai
Manufacturing austenite stainless steels (ASSs) using additive manufacturing (AM) is of great interest for cryogenic applications. Here, the mechanical and microstructural responses of a 316L ASS built by laser powder-bed-fusion (L-PBF) were revealed by performing in situ neutron diffraction tensile tests at the low-temperature range (from 373 to 1…
PreprintO.Crofts A.Loving M.Torrance S.Budden B.Drumm T.Tremethick D.Chauvin M.Siuko W.Brace V.Milushev M.Mittwollen T.Lehmann F.Rauscher G.Fischer P.Pagani Y.Wang C.Baars A.Vale
During the EU DEMO Pre-Concept Design Phase, the remote maintenance team developed maintenance strategies and systems to meet the evolving plant maintenance requirements. These were constrained by the proposed tokamak architecture and the challenging environments but considered a range of port layouts and handling system designs. The design‑d…
Preprint PurchaseTay 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 PurchaseH. Anand D. Eldon H. Q. Wang G. McArdle L. Pangione M. Kochan
A local flux expansion method has been proposed for estimating the strike point position for the advanced divertor configuration on MAST Upgrade tokamak. The paper discusses the application and assesses the performance of the technique on a long-legged divertor plasma configuration on an operating device – the DIII-D tokamak. A comparison of …
Preprint PurchaseJ. Peng H Zhang Y. Wang M. Richardson X. Liu D. Knowles M. Mostafavi
The small punch test (SPT) has been widely used to evaluate the mechanical properties of materials for the nuclear industry due to its advantage of requiring minimal sample volumes. In this paper, the correlation between SPT and uniaxial tensile testing (UTT) is investigated for three materials used in the plasma-facing components of fusion reactor…
Preprint PurchaseBin 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 …
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