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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)822018
The containment vessel of the Joint European Torus is a huge, complicated assembly with a myriad of components, all of which are important for plasma operation. As a research device, JET has been operated over many years and has been extensively rebuilt. During each maintenance shutdown, inspections and measurements of the Vacuum Vessel are carri…
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UKAEA-CCFE-PR(25)3971970
In this work, atom probe tomography has been applied to study lithium-induced corrosion of Pulsed-Laser Deposition grown Al2O3, which is a candidate coating material for the breeder blankets of nuclear fusion reactors. Samples were immersed in static Pb-17Li for 7000h with samples extracted from the regions near the ceramic-substrate interface t…
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CLM P921965
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CLM P781965
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UKAEA-CCFE-PR(19)572019
By mixing elements with favourable nuclear activation properties to create high-entropy alloys, it may be possible to create a material that can withstand a nuclear fusion environment while minimising the radioactive waste produced. Such a material could be used in the extreme thermal and irradiation conditions of a fusion blanket. A suite of previ…
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UKAEA-CCFE-PR(19)422019
High temperature, neutron irradiated single crystal tungsten, with a post irradiation composition of W-1.20±0.11at.%Re-0.11±0.05at.%Os-0.03±0.01at.%Ta was characterised using a combination of Atom Probe Tomography (APT) and Scanning Transmission Electron Microscopy (STEM). APT showed that within nanoscale clusters of Re/Os, the atomic density wa…
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UKAEA-CCFE-CP(18)122018
RACE has been developing a concept design for the remote maintenance system for the EUROfusion DEMO powerplant. Within the DEMO tokamak, tritium breeding blankets will require periodic replacement which is currently designed to utilize the upper vertical ports at the top of the vacuum vessel. This operation will be challenging due to the scale of t…
Showing 11 - 18 of 18 UKAEA Paper Results