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UKAEA-CCFE-PR(23)1592023
Fusion power output from spherical tokamaks would benefit from increased confined plasma density, but there exists a limit on the density before confinement is lost and the plasma current is disrupted. This density limit has long been characterized by a simple, global Greenwald limit proportional to the plasma current and inversely proportional …
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UKAEA-CCFE-CP(23)602022
Diamond’s intrinsic hardness, excellent thermal conductivity and low atomic number make it a highly promising candidate as a plasma facing material. However, as with the previously used graphite, concerns over tritium retention and resultant chemical etching have so far limited research interest in the use of synthetic diamond. In order to study …
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UKAEA-CCFE-PR(23)1612023
Severe plasma transients such as disruptions will impose high magnitude, short duration thermal loads on the plasma-facing first wall of the EU’s DEMOnstration tokamak. Repeated over DEMO’s lifetime, these transients may cumulatively alter the microstructure of first wall structural materials, degrading their performance. The effects of repeate…
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UKAEA-CCFE-CP(23)622023
The UK National Nuclear Laboratory (NNL) has been developing its capability in high‑temperature water corrosion over the past years in collaboration with the University of Bristol, UK. As part of this work, studies have been undertaken on nuclear fusion‑specific material Eurofer‑97, a reduced activation ferritic‑martensitic steel. Eurofe…
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UKAEA-CCFE-CP(23)632023
The real time plasma control system for the MAST Upgrade tokamak has been substantially redeveloped from its original MAST incarnation with a new architecture that aims to manage complexity whilst maximising flexibility. It provides modular layers of functionality and supports the implementation of virtual actuators to aggregate, arbitrate and rout…
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UKAEA-CCFE-PR(23)1662023
MAST-Upgrade (MAST-U) is undergoing several enhancements to deliver increased performance and functionality. One such enhancement is the design, development, and implementation of an Electron Bernstein Wave (EBW) Heating and Current Drive (HCD) System. The MAST-U EBW System aims to provide experimental data for model validation, and to provide a…
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UKAEA-CCFE-PR(23)1642023
The present paper is dedicated to the study of the discrepancies encountered in electron temperatures (Te) measurements carried out with Electron Cyclotron Emission (ECE) and Thomson Scattering (TS) diagnostics in the core of the JET tokamak. A large database of discharges has been collected, including high-performance scenarios perform…
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UKAEA-CCFE-PR(23)1752022
In-vessel plasma facing components in fusion reactors such as ITER and DEMO experience high thermal loads and require active cooling, for which water is one possible coolant. The solution where plasma facing components utilise tungsten blocks as sacrificial armour has a joint internal structure of cooling tubes made from the copper base (~99% Cu…
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UKAEA-CCFE-PR(23)1742022
Understanding the effects of interfacial micro-structures/-defects such as voids, grain boundaries (GB) and partial recrystallization (Rx) is critical to achieving superior mechanical properties for safety-critical parts. These features may appear during advanced manufacturing processes such as sintering, additive manufacturing (AM), and diffusi…
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UKAEA-CCFE-PR(23)1732023
While modern nuclear decay data can provide many details of a given nuclides β-decay modes (branching ratios, decay heating etc), knowledge of the emitted β-energy spectrum is often not included. This limitation hampers the use of decay data in some analysis, such as β-spectrometry of irradiated material, prediction of β-decay Bremsstrahlung…
Showing 381 - 390 of 2527 UKAEA Paper Results