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UKAEA-CCFE-CP(23)022023
Understanding the plasma parameters that affect the scrape off layer (SOL) width is a key issue for future tokamaks as the power entering the SOL (of order 100 MW [1] in ITER) and the SOL width (of order millimetres [2]) determine the heat flux to the divertor surfaces. The Eich scaling [2] can be used to characterise the divertor heat flux prof…
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UKAEA-CCFE-PR(23)112023
A prototype infrared video bolometer (IRVB) was succesfully deployed in MAST-U, the first deployment of such a diagnostic in spherical tokamaks. The IRVB was designed to study the radiation around the x-point and has the potential to return emissivity profiles of unprecedented spatial resolution. The system was fully characterised prior installatio…
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UKAEA-CCFE-PR(23)072023
A Tritium fuel cycle must have the capability to import tritium inventory from transport storage containers to enable initial inventory stockpiling and future refresh of the inventory. The Joint European Torus (JET) Active Gas Handling System (AGHS) previously imported tritium inventory from Amersham Uranium beds (U-beds) via a decanting system hou…
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UKAEA-CCFE-PR(23)062023
The Exhaust Detritiation System (EDS) of the JET Active Gas Handling System (AGHS) removes tritium from exhaust gases and contaminated air prior to discharge to stack. The system was replaced prior to JET’s tritium experimental campaign due to corrosion damage. In this paper, the following topics are presented: System function and de…
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UKAEA-CCFE-PR(23)042023
The High Field High Density Region (HFSFD) has been experimentally observed in both divertor and limiter tokamak devices. In order to numerically reproduced the HFSHD region in the limiter tokamak device J-TEXT, we first performed SOLPS-ITER simulations on the J-TEXT limiter tokamak with the activation of drifts, which is associated with the HFSHD …
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UKAEA-CCFE-PR(23)032023
Spherical tokamaks are key for the successful design of operating scenarios of future fusion reactors in the areas of divertor physics, neutral beam current drive and fast ion physics. MAST Upgrade, which has successfully concluded its first experimental campaign, was specifically designed to address the role of the radial gradient of the fast ion…
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UKAEA-STEP-CP(25)022022
Estimating costs of prototype or demonstration fusion power plants is difficult enough due to the often still preliminary designs combined with a non-existing supply chain for many bespoke technologies or materials. Extrapolating to commercial fusion power plants without a clear design is even harder and uncertainties are large. As a result, for…
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UKAEA-CCFE-CP(25)032022
The UK Spherical Tokamak for Energy Production (STEP) program is currently progressing the conceptual engineering design of a Spherical Tokamak-based fusion reactor. The program includes a project concerned with design of the reactor breeding blanket. The objective of this work was to develop a low fidelity, integrated simulation approach to sup…
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UKAEA-CCFE-PR(25)2812022
Commercial fusion energy will require an energy-producing fusion plasma core (the “fire”) surrounded by an integrated engineering system (the “fireplace”). This review focuses on the extreme materials requirements of the fusion “fireplace,” which has the following intertwined functions: (1) a first wall that faces and survives the inten…
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UKAEA-CCFE-PR(25)2802022
In this work a spatial dimension is added to the description of radiative detachment in MAST-U super-X divertor plasmas. This magnetic configuration is hypothesized to achieve improved heat load spreading at the divertor target and more particle-, heat- and momentum losses through plasma-neutral interactions than conventional exhaust solutions. Fil…
Showing 91 - 100 of 353 UKAEA Paper Results