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UKAEA-CCFE-CP(20)1002020
Disruption prediction and avoidance is necessary in future MAST-U spherical tokamak discharges to enable long-pulse plasma operation. Research examining the stability of plasmas in the MAST database utilizing proposed high quality kinetic equilibrium reconstructions and calculations with various codes, including the Disruption Event Characterizatio…
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UKAEA-CCFE-CP(23)562019
An important area of research required for fusion reactor design is the study of materials under high energy neutron irradiation. Deuterium-Tritium (D-T) reactions release 14.1 MeV neutrons and material studies of such high energy neutrons focusing on transmutation and activation are paramount for fusion tokamak devices such as ITER and DEMO. Th…
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UKAEA-CCFE-CP(23)092019
Recent studies of the neutron irradiation conditions predicted in the plasma-exposed first wall of a conceptual design of fusion DEMO power plant implementing the SPECTRA-PKA code have shown the importance of taking into consideration per-channel analysis of the high-energy threshold reactions for an accurate evaluation of their contribution to …
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UKAEA-CCFE-CP(20)812018
The Alfvén Eigenmode Active Diagnostic system (AEAD) has undergone a major upgrade and redesign to provide a state of the art excitation and real-time detection system for JET. The new system consists of individual 4kW amplifiers for each of the six antennas, allowing for increased current, separate excitation and real time control of relative …
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UKAEA-CCFE-CP(20)802018
The European DEMO design will potentially use single phase water cooling in various components that require protection against corrosion damage. Coolant conditions will be similar to fission PWRs but with additional considerations arising from the materials of choice (Eurofer, CuCrZr), 14 MeV neutron irradiation, the presence of tritium, and strong…
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UKAEA-CCFE-PR(20)022019
Shear strain profiles along slip bands in a modified Rolls-Royce nickel superalloy (RR1000) were analyzed for tensile sample deformed by 2%. The strain increased with distance away from a grain boundary (GB), with maximum shear strain towards the center of the grain, indicating that dislocation nucleation generally occurred in the grain interior. T…
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UKAEA-CCFE-CP(19)452019
Spherical Tokamaks offer a number of potential advantages for a future fusion power plant. They have a high ratio of thermal to magnetic field pressure (beta) and strong flows, either of which could result in reduced turbulence. Fewer Toroidal Field (TF) coils and a different geometry offers the potential for new methods of remote maintenance …
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UKAEA-CCFE-CP(19)422019
Plasma detachment needs to be achieved in ITER [1] and future devices such as DEMO to dissipate most of the power in the Scrape-Off-Layer (SOL) and reduce the particle flux reaching the divertor targets. In order to enhance our capability to improve current, and design future tokamaks, we must improve our understanding of the relative effect on det…
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UKAEA-RACE-CP(19)012019
Remote inspection of a complex environment is a difficult, time consuming task for human operators to perform. The need to manually avoid obstacles whilst considering other performance factors i.e. time taken, joint effort and information gained represents significant challenges to continuous operation. This paper proposes an autonomous robotic so…
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UKAEA-CCFE-PR(19)592019
We perform a study of system-scale to gyro-radius scale electromagnetic modes in a pedestal-like equilibrium using a gyrokinetic code ORB5, and compare to the results of a local gyrokinetic code, GS2, and an MHD energy principle code, MISHKA. In the relevant large-system, short wavelength regime, good agreement between the gyrokinetic codes is foun…
Showing 81 - 90 of 183 UKAEA Paper Results