F. Schoofs F. Ji A. D. L. Hancock H. J. Lewtas
The atmosphere in powder-based additive manufacturing influences the level of impurities inside the build volume as well as the phases formed during cooldown. We use a thermodynamic model to investigate trends for steels commonly considered for fusion reactors and power plants, namely 316L, F91, F92 and Eurofer97. The atmospheres considered are …
PreprintR. Kembleton W. Morris G. Federicia A. J. H. Donné
The EUROfusion Roadmap for fusion research was recently updated and describes a clear set of missions and associated goals on the route to commercial fusion electricity. Beyond ITER, the main target of the programme is the development of DEMO, a fusion technology demonstrator which will produce substantial net electrical output, breed its own fu…
Preprint PublishedThomas R. Barrett T. Grant M. Kovari N. Mantel A. Muir
Investment in past fusion experiments has been motivated largely by the study of tokamak physics, and has been vital to provide a sound physics basis for design of a power reactor. However, meeting the challenge of realising fusion energy production will require considerable and increasing investment in facilities for testing and development of fus…
Preprint PublishedA. Valentine B. Colling R. Worrall J. Leppänen
Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, such as shielding, material lifetime and remote maintenance requirements/scheduling. Neutronics studies are performed using radiation transport codes such as MCNP, TRIP…
Preprint PublishedIan Chapman Nick Walkden
Fusion energy is an area of active development and innovation worldwide, with many design concepts exhibiting a range of technical challenges. A significant portion of technical challenges will be unique for a given design concept, however there are several overarching challenges that any design must address to some degree. These include: Tritiu…
Preprint PublishedJ. Morris M. Y. Ye S. Mao
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
Preprint PublishedC Harrington A Baron-Wiechec R Burrows R Holmes R Clark S Walters T Martin R Springell J Öijerholm R Becker
The European DEMO design will potentially use single phase water cooling in various components that require protection against corrosion damage. Coolant conditions will be similar to fission PWRs but with additional considerations arising from the materials of choice (Eurofer, CuCrZr), 14 MeV neutron irradiation, the presence of tritium, and strong…
Preprint PublishedStuart I. Muldrew Felix Warmer Jorrit Lion Hanni Lux
With a lack of plasma disruptions and current-driven instabilities, stellarators are potentially an attractive option for a fusion power plant. Previous system studies have been performed to optimise a HELIAS (HELIcal-axis Advanced Stellarator) 5-B power plant using PROCESS, however these have been based around a single design point. In reality …
Preprint PublishedYiqiang Wang Omar Mohamed Keren Dunn Tan Sui Mutaz Bashir Peter Copper Adomas Lukenskas Guiyi Wu Michael Gorley
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…
Preprint PublishedAlexander J. Leide Richard. Todd David E. J. Armstrong
Focussed ion beam (FIB) milling can be used to reveal sub-surface fracture and deformation below indents in materials. However, evolution of residual stresses around the indent impression cause changes to the crack morphology during the FIB cross-sectioning procedure. Berkovich nanoindents in single crystal hexagonal (6H) silicon carbide cause r…
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