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UKAEA-STEP-PR(24)212024
The design, delivery, and operation of a large-scale infrastructure project is challenging at best. For the Spherical Tokamak for Energy Production (STEP) Prototype Powerplant (SPP), the challenges increase exponentially. In addition to being a large-scale infrastructure project, it is a cutting edge, first of a kind (FOAK) technology demonstrat…
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UKAEA-STEP-PR(24)222024
The architecture of STEP has been developed to enable a hybrid maintenance approach, using ports in the vacuum vesselor a limited list of tasks that must be performed shortly after shutdown, and larger openings to simplify and speed-up major refits. Robotic handling systems in zero-human entry facilities will prevent workers from being exposed t…
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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…
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UKAEA-CCFE-PR(24)2692024
The paper provides an assessment of the ion-cyclotron resonance heating (ICRH) system performance on JET since the year 2000. The vast amount of collected data offer an insight into the historical challenges and trends in the ICRH system performance encompassing the transition from carbon (JET-C) to beryllium (JET‑Be) first wall operations, th…
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UKAEA-CCFE-CP(24)132024
An overview of the modelling approaches, validation methods and recent main results of analysis and modelling activities related to the plasma-wall interaction in JET-ILW experiments, including the recent H/D/T campaigns is presented in the paper. Code applications to JET-ILW experiments improve general erosion/migration/retention prediction cap…
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UKAEA-CCFE-PR(24)2652024
Dedicated experiments were performed on MAST Upgrade to study beam-ion losses caused by charge exchange (CX) with edge neutrals. The fuelling was switched from the high-field side to the low-field side mid-discharge. Direct measurements suggest a strong increase in neutral density around the plasma and a deterioration of the beam-ion confinement…
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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-CP(24)142023
Accurate quantification of the power loss channels and overall power balance of the plasma is essential for the safe operation of current and future fusion devices. The relative magnitudes of core radiation, SOL radiation and divertor target heat loading are determining factors in both PFC design and plasma scenario design in the successful real…
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UKAEA-CCFE-PR(24)2662024
A new type of resonant magnetic perturbation (RMP), generated by helical coils, is proposed for controlling the edge localized mode (ELM) in H-mode tokamak plasmas. The helical coil optimization utilizes the MARS-F code (Liu et al 2000 Phys. Plasmas 7 3681) computed linear resistive fluid response of the plasma to the applied RMP field. The opti…
Showing 241 - 250 of 2527 UKAEA Paper Results