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UKAEA-CCFE-CP(20)942018
Edge localised modes (ELMs) are magneto-hydrodynamic (MHD) instabilities that drive filamentary plasma eruptions in high confinement tokamak discharges [1]. Gaining an improved understanding of ELMs is important [2]; in future fusion reactors such as ITER, ELM heat fluxes will need to be limited to ensure durability of divertor materials [3]. A …
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UKAEA-CCFE-CP(20)952018
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UKAEA-CCFE-CP(20)882018
The ASDEX Upgrade (AUG) programme is geared towards developing the physics basis for ITER and (EU)-DEMO and is jointly executed with the EUROfusion Medium Size Tokamak task force. Integrated scenario development to prepare future device operation, detailed physics studies to improve predictability of fusion devices and testing of fusion relevant t…
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UKAEA-CCFE-CP(20)872019
Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, such as shielding, material lifetime and remote maintenance requirements/scheduling. Neutronics studies are performed using radiation transport codes such as MCNP, TRIP…
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UKAEA-CCFE-PR(20)942020
Fusion energy is an area of active development and innovation worldwide, with many design concepts exhibiting a range of technical challenges. A significant portion of technical challenges will be unique for a given design concept, however there are several overarching challenges that any design must address to some degree. These include: Tritiu…
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UKAEA-CCFE-PR(20)932020
Parametric dependencies of the linear stability of toroidal Alfven eigenmode (TAE) in the presence of neutral beam injection (NBI) are investigated to understand the beam drive and damping effect of TAEs in JET and KSTAR. It is found that the results depend on the drift orbit width of the beam-ions normalized to the characteristic mode widths. I…
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UKAEA-CCFE-CP(20)852020
The anticipated heat flux limit of the European DEMO first wall is ~1MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than that the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected in such events. This involves de…
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UKAEA-RACE-CP(20)022020
As part of the development work performed under the ITER Robotic Test Facility (IRTF) the development and substantiation of the maintenance strategy for the Vacuum Vessel Pressure Suppression System (VVPSS) must be investigated. The VVPSS is a key safety aspect of the vacuum vessel of ITER. It ensures after a coolant leak, and subsequent pressure e…
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UKAEA-CCFE-CP(20)862018
Nuclear fusion is the process that heats the stars by the collision of atomic nuclei which fuse together to form heavier elements and release energy. The generation of energy using this process has several advantages: no carbon emissions, abundant fuel supplies, efficiency, reliability and operationally safe. One way to achieve the necessary con…
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UKAEA-CCFE-CP(20)842019
JET has now completed three operating periods, ILW1, ILW2 and ILW3, giving an opportunity to make comparisons between tiles exposed for single operating periods and also comparisons of tiles exposed for all three periods, ILW1-3 (2011-2016). In this contribution, a comprehensive overview of fuel retention and material erosion/deposition patterns…
Showing 871 - 880 of 2527 UKAEA Paper Results