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UKAEA-STEP-PR(25)312024
A strategy to prevent concentrated deposition of the exhaust power in a fusion device is to seed a localised ‘divertor’ region with impurity gas, which is chosen to radiate predominantly at the cooler electron temperatures associated with the plasma edge. If this impurity travels upstream to the main confined plasma, it can significantly impact…
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UKAEA-CCFE-PR(25)3202024
The development of a high current baseline scenario (I_p = 3.5MA, q95 ~3.0, beta_N < 2) in deuterium (D), tritium (T) and deuterium-tritium (D-T) for high DT fusion performance at JET with Be/W wall is described. We show that a suitable scenario capable of delivering up to 10 MW of fusion power, depending on the auxiliary heating power avail…
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UKAEA-CCFE-CP(25)092024
The successful development of fusion power will rely on the key technology of breeder blanket components. These components surround the fusion plasma, providing significant heat for power generation, and breeding the tritium fuel on which the plasma reaction depends. However, the technology for these components remains at a low technology readin…
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UKAEA-CCFE-PR(25)2972024
During detachment, a buffer of neutral atoms and molecules builds up between the target and the ionising plasma. Collisions between the plasma and the molecules play an important role in the detachment process. Studies of plasma-molecular kinetics indicate that the gas temperature is increased during detachment for a wide range of conditions on …
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UKAEA-CCFE-PR(25)2692024
A linear-elastic computer simulation (model) for a single particle of TRISO fuel has been built using a bond-based peridynamic technique implemented in the finite element code ‘Abaqus’. The model is able to consider the elastic and thermal strains in each layer of the particle and to simulate potential fracture both within and between layers…
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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-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)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-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)202024
Success of UKs STEP (Spherical Tokamak for Energy Production) programme [1] [2] [3] [4] requires a robust plasma control system. This system has to guide the plasma from initiation to the burning phase, maintain it there, producing the desired fusion power for the desired duration and then terminate the plasma safely. This has to be done in a ch…
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