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UKAEA-STEP-CP(24)052023
The STEP (Spherical Tokamak for Energy Production) Programme aims to deliver a UK prototype fusion energy plant, targeting 2040, and a path to commercial viability of fusion. To deliver on this aim, we have performed initial scoping to identify the design point for a spherical tokamak prototype powerplant producing at least 100 MWe of…
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UKAEA-CCFE-PR(24)2492023
Short-range order (SRO) in multicomponent concentrated alloys affects their mechanical response. Hence, is paramount to understand how composition modifies the chemical ordering in the system to design materials with optimal properties. We present here a methodology to predict the SRO and thermodynamic properties in chemically complex systems an…
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UKAEA-CCFE-PR(24)2212023
Titanium and chromium beryllides, TiBe12 and CrBe12, are materials of potential future importance as neutron multipliers for tritium breeding in nuclear fusion reactors. Beryllium experiences extremely high transmutation according to a n →2n transmutation reaction in which both tritium and helium are produced, which norma…
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UKAEA-CCFE-CP(22)082022
The charged particle heat load assessed for the DEMO Single Module Segment First Wall (FW) during current off-normal plasma scenarios underlines that protection is needed for avoiding/reducing damage to the Breeding Blanket FW due to the deposition of a huge amount of energy in a small timescale. Within the “Key Design Integration Issue 1”, an…
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UKAEA-RACE-CP(21)042021
Just like most industrial or scientific installations, future fusion reactors will require more or less frequent maintenance. The expected environmental conditions, as well as the necessity of carrying out many maintenance tasks in parallel in result in remote robotic maintenance becoming a necessity in order to minimize the maintenance shutdown du…
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UKAEA-CCFE-CP(20)822018
The containment vessel of the Joint European Torus is a huge, complicated assembly with a myriad of components, all of which are important for plasma operation. As a research device, JET has been operated over many years and has been extensively rebuilt. During each maintenance shutdown, inspections and measurements of the Vacuum Vessel are carri…
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UKAEA-CCFE-CP(19)502019
Within the framework of EUROfusion DEMO First Wall and limiter design activities, the protection of the First Wall against power deposition peaks is being considered. During steady-state operation, the radiative power from the plasma could be considered uniformly spread on plasma-facing components. However, the presence of openings (i.e. g…
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UKAEA-CCFE-PR(19)762019
Shutdown dose rate calculations provide an essential input to the design and research of fusion power plant technology. They allow the estimation of dose to personnel and equipment during planned and unplanned maintenance. The mesh coupled rigorous 2 step (MCR2S) methodology used at Culham Centre for Fusion Energy (CCFE) was originally developed to…
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UKAEA-CCFE-PR(19)572019
By mixing elements with favourable nuclear activation properties to create high-entropy alloys, it may be possible to create a material that can withstand a nuclear fusion environment while minimising the radioactive waste produced. Such a material could be used in the extreme thermal and irradiation conditions of a fusion blanket. A suite of previ…
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UKAEA-CCFE-CP(18)122018
RACE has been developing a concept design for the remote maintenance system for the EUROfusion DEMO powerplant. Within the DEMO tokamak, tritium breeding blankets will require periodic replacement which is currently designed to utilize the upper vertical ports at the top of the vacuum vessel. This operation will be challenging due to the scale of t…
Showing 1 - 10 of 13 UKAEA Paper Results