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UKAEA-CCFE-PR(25)3332024
The plasma-facing components of nuclear fusion reactors are continuously subjected to high thermal loads and bombardment by hydrogenic ions, resulting in erosion of the first-wall material and sputtering of atomic and molecular species into the edge plasma. The management of reactor component lifetimes and control of sputtered plasma impurities r…
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UKAEA-CCFE-PR(25)3262024
In this paper,we examine the role of the aspect ratio on the neutral penetration and poloidal distribution for fixed magnetic geometry and plasma profiles using SOLPS-ITER. We start from an H-mode discharge from MAST [9], with its aspect ratio of 1.4 and shift the magnetic equilibrium and vessel in major radius to generate a new SOLPS-ITER simul…
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UKAEA-CCFE-CP(25)132024
The end of tokamak operations at the Joint European Torus in December 2023 brought to a close the experimental life of an extraordinary fusion research facility.
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2024
This paper presents a detailed user study aimed at experimentally comparing the experience levels within bilateral teleoperation. The primary objective is to elucidate the key performance metrics that can effectively evaluate the competency level of human operators. Existing methodologies typically focus on the quantitative psychological evaluatio…
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UKAEA-CCFE-PR(25)2762024
Creep-fatigue damage has been recognised as a critical failure mode for high-temperature structures. In fusion power reactors, plasma-facing components endure complex loading conditions, resulting in high thermomechanical stresses. These components, often made from 316L material, joined to ferritic-martensitic steels, face significant challenges du…
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UKAEA-CCFE-PR(25)2662024
This paper reports on a FEM-based computational methodology to assess dynamic amplification factors (DAF) of a divertor cassette, under electromagnetic (EM) impact loads caused by a plasma disruption event. The investigation concerns a typical divertor cassette body (CB) of the European DEMO reactor (baselin…
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UKAEA-STEP-PR(25)242024
The UKAEA’s Spherical Tokamak for Energy Production (STEP) programme aims to demonstrate the ability of low aspect ratio tokamaks to generate net electricity from deuterium-tritium (DT) fusion. As STEP have selected REBCO coated conductor (CC) as the current carrier in most magnet systems, understanding how REBCO CC responds to the energetic p…
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UKAEA-CCFE-PR(24)2702024
Plasma turbulence on disparate spatial and temporal scales plays a key role in defining the level of confinement achievable in tokamaks, with the development of reduced numerical models for cross-scale turbulence effects informed by experimental measurements an essential step. MAST-U is a well-equipped facility having instruments to measure ion …
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UKAEA-CCFE-PR(24)2682024
Silicon carbide fibre reinforced silicon carbide matrix composite (SiC/SiC) is a key structural material for fusion reactors to allow high temperature operation of liquid lithium breeder blankets. This research investigated the corrosion behaviour of two SiC/SiC composites (using Tyranno SA3 and SA4 fibres) immersed in static liquid lithium at 6…
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UKAEA-CCFE-PR(24)2672024
The self-passivating yttrium-containing WCr alloy has been developed and researched as a potential plasma-facing armour material for fusion power plants. This study explores the use of yttria (Y2O3) powders instead of yttrium elemental powders in the mechanical alloying process to assess their applicability in this material. Fabricated through f…
Showing 51 - 60 of 438 UKAEA Paper Results