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UKAEA-CCFE-PR(23)092023
Following from the paper describing the remote wide angle viewing system compatible with Deuterium-Tritium operations. This is the second article describing a second remote line of sight, this time focusing on the imaging of the divertor region in JET. It explains in detail the optical and engineering designs of constructing an optical relay which …
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UKAEA-CCFE-PR(23)082022
The role of ion-molecule elastic collisions (specifically D+−D2 collisions) in strongly detached divertor conditions has been studied in the MAST-U Super-X configuration using SOLPS-ITER. Two strongly detached steady state solutions, one obtained through a main-ion (D2) fuelling scan and the other through an impurity (N) seeding scan at fixed …
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UKAEA-CCFE-CP(23)012023
The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power in 2019–2020, and …
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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)052023
Predictions of material activity in commercial fusion conditions predominantly rely on computational methods, due to a lack of data on long-term e ects of high-energy neutron irradiation on structural steels. Consequently, this could result in a bias due to uncertainties in nu…
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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-CCFE-PR(23)022023
A toroidal Alfven eigenmode (TAE) has been observed driven by alpha particles in the Joint European Torus (JET). The observation was made in dedicated deuterium-tritium experiments where radio-frequency (RF) heating was absent, in the so-called “afterglow” period when neutral beam heating was removed. Agreement with reduced and perturbative mod…
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UKAEA-CCFE-PR(23)012022
The design and understanding of alternative divertor configurations may be crucial for achieving acceptable steady-state heat and particle material loads for magnetic confinement fusion reactors. Multiple x-point alternative divertor geometries such as Snowflakes and Xpoint targets have great potential in reducing power loads, but have not yet b…
Showing 571 - 580 of 2527 UKAEA Paper Results