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UKAEA-CCFE-PR(23)902020
Plasma-wall interactions in a commercial-scale fusion power station may exert high transient thermal loads on plasma-facing surfaces, repeatedly subjecting underlying structural materials to high temperatures for short durations. Specimens of the reduced activation ferritic-martensitic steel Eurofer-97 were continuously aged at constant temperat…
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UKAEA-CCFE-CP(20)1172020
The next generations of nuclear fusion reactors, including ITER and DEMO, will consider several different cooling systems for heat dissipation, power generation and tritium breeding. This includes the water-cooled lithium-lead blanket (WCLL) design, which bears significant similarities to the water-cooled circuit in a pressurised water fission reac…
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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-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(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)502019
A model for a beam-driven plasma neutraliser for a 1MeV, 40A beam of D- ions is presented and is based on the dimensions of the ITER gas neutraliser. For the beam-driven plasma neutraliser there is no need for an external power source for producing and sustaining the plasma. Instead the use of high magnetic fields is employed for plasma confinement…
Showing 11 - 20 of 42 UKAEA Paper Results