J. Morris M. Coleman S. Kahn A. J. Pearce D. Short J. E. Cook S. Desai L. Humprey M. Kovari J. Maddock D. Vaccaro
As the EUROfusion EU-DEMO design programme approaches the transition between the pre-conceptual and conceptual design phase the systems code PROCESS has been improved to incorporate more detailed plasma physics, engineering and analysis modules. Unlike many systems codes PROCESS combines the physics modelling with both technology and costs analysis…
PreprintM. Fulvio L. Aho-Mantila R. Ambrosino T. Body H. Bufferand G. Calabro’ G. Ciraolo D. Coster G. Di Gironimo P. Fanelli N. Fedorczak A. Herrmann P. Innocente R. Kembleton T. Lunt D. Marzullo S. Merriman D. Moulton A. Nielsen J. Omotani G. Ramogida H. Reimerdes M. Reinhart P. Ricci F. Riva A. Stegmeir F. Subba W. Suttrop P. Tamain M. Teschke A. Thrysoe W. Treutterer S. Varoutis M. Wensing M. Wischmeier l. Y. Xiang J. Lilburne A. Wilde
A comparison between different alternative divertor configurations, in terms of benefits and additional complexity is carried out for the European DEMO. A synergetic approach between different aspects of the problem, including physics and engineering, provides new insight on the capabilities of the new divertors to handle the exhausted power wit…
PreprintDamian Sobieraj Jan S. Wróbel Mark R. Gilbert Andrey Litnovsky Felix Klein Krzysztof J. Kurzydłowski Duc Nguyen-Manh
W-Cr-Y smart alloys are potential material candidates for plasma facing components due to their protective behaviour during the loss-of-coolant accident (LOCA), while maintaining beneficial properties of W during the normal operation of the fusion power plant. During plasma exposure the lighter alloying elements are preferentially sputtered at t…
PreprintD. Nguyen-Manh J.S. Wrobel M. Klimenkov M.J. Lloyd L. Messina S.L. Dudarev
Understanding how properties of materials change due to nuclear transmutations is a major challenge for the design of structural components for a fusion power plant. In this study, by combining a first-principles matrix Hamiltonian approach with thermodynamic integration we investigate quasisteady state configurations of multi-component alloys, …
PreprintD.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 PublishedJ. R. Harrison T. Farley G. M. Fishpool A. Kirk B. Lipschultz J. Lovell F. Militello D. Moulton P. Ryan R. Scannell A. J. Thornton K. Verhaegh L. Xiang
The benefits of an optimised Super-X divertor configuration in mitigating the steady-state power and particle fluxes to the surfaces of the MAST Upgrade divertor have been quantified by performing a detailed comparison with a conventional divertor for the first time. In otherwise identical plasmas with conventional and Super-X divertor configu…
PreprintJ. Fradera S. Sadaba F. Calvo S. Ha S. Merriman P. Gordillo J. Connell A. Elfaraskoury B. Echeveste
As part of the UKAEA Spherical Tokamak for Energy Production (STEP) fusion power station programme, a novel breeding blanket design was assessed. A conceptual design of STEP, which will be an innovative plan for a commercially-viable fusion power station, will be completed by 2024. The final aim of the current assessment is to find a conceptual des…
Preprint PublishedS. Kirk K. Keogh
The maintenance and decommissioning of nuclear reactors requires the rapid cutting and welding of thick-walled pipework, to which laser processing is highly suited. However, the large size and stand-off of current laser heads precludes their use in space constrained areas and incorporation into in-bore processing tools. To address this, novel minia…
Preprint PublishedA. Loarte A. R. Polevoi M. Schneider S.D. Pinches E. Fable E. Militello Asp Y. Baranov F. Casson G. Corrigan L. Garzotti D. Harting P. Knight F. Koechl V. Parail D. Farina L. Figini H. Nordman P. Strand R. Sartori
The optimum conditions for access to and sustainment of H-mode plasmas and their expected plasma parameters in the Pre-Fusion Power Operation 1 (PFPO-1) phase of the ITER Research Plan, where the additional plasma heating will be provided by 20 MW of Electron Cyclotron Heating (ECH), are assessed in order to identify key open R&D issues. The as…
Preprint PublishedS. Mijin F. Militello S. Newton J.T. Omotani R.J. Kingham
We present the first parallel electron transport results obtained using the newly developed 1D transport code SOL-KiT. In order to properly predict divertor heat loads it is of key importance to develop a thorough understanding of discrepancies between different parallel transport modelling approaches. With the capability to self-consistently sw…
Preprint Published