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UKAEA-CCFE-PR(26)4062025
Neutron bombardment of high temperature superconducting (HTS) magnets may compromise the integrity of the magnetic confinement in future fusion reactors. The amount of damage produced by a single neutron can be predicted from the threshold displacement energies (TDE) of the constituent ions in the HTS materials, such as the Rare Earth Cuperates.…
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UKAEA-CCFE-PR(24)2272024
Tungsten is one of the primary materials for several applications in commercial fusion power plant designs, in particular for divertor targets and the first wall. In maintenance conditions or during a loss of coolant accident, tungsten is expected to reach temperatures at which it readily volatilises as tungsten trioxide in contact with air, potent…
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UKAEA-CCFE-PR(24)2182024
Mixed convection of an electrically conductive fluid in a square duct with imposed transverse magnetic field is studied using Large Eddy Simulation (LES) paradigms. The duct walls are electrically conductive, with the wall conductivity parameter cw ranging from 0 to 0.5. The Reynolds number is Re = 5602 and the Prandtl number is Pr = 0.0238. The fo…
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UKAEA-CCFE-PR(25)3492023
Tungsten is one of the primary materials of choice for several commercial fusion power plant designs, in particular for divertor targets and first wall. In maintenance conditions or during a loss of coolant accident, tungsten is expected to reach temperatures at which it readily volatilises as tungsten trioxide, potentially distributing radioactive…
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UKAEA-CCFE-PR(24)2192023
Heat transfer is a key consideration in the development of tritium breeder blankets for future fusion reactors. For solid tritium breeder materials there is a a fine balance to be struck between high levels of porosity to encourage tritium release and minimising it to maintain the thermal and mechanical properties. Therefore, in this work we emp…
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UKAEA-CCFE-PR(23)842023
We present a numerical model to predict oxide scale growth on tungsten surfaces under exposure to oxygen at high temperatures. The model captures the formation of four thermodynamically-compatible oxide sublayers, WO2, WO2.72, WO2.9, and WO3, on top of the metal substrate. Oxide layer growth is simulated by tracking the oxide/oxide and oxide/metal …
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UKAEA-CCFE-PR(23)1122022
The transfer of heat through the breeder region of a future fusion reactor is a key component of its thermal efficiency. Development of advanced ceramic breeder materials based on Li2TiO3 seek to exploit its ability to accommodate significant non-stochiometry, however, it is not clear how deviations for the 50:50 mix of Li2O and TiO2 will affect…
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UKAEA-CCFE-PR(22)042022
The small punch test (SPT) has been widely used to evaluate the mechanical properties of materials for the nuclear industry due to its advantage of requiring minimal sample volumes. In this paper, the correlation between SPT and uniaxial tensile testing (UTT) is investigated for three materials used in the plasma-facing components of fusion reactor…
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UKAEA-CCFE-PR(21)532021
The high anisotropy in the thermal conductivity of lithium metatitanate, Li2TiO3, is shown using the classical simulation method of Molecular Dynamics (MD). The thermal conductivity along the z-direction is markedly lower than that in x and y. This characteristic could be exploited to favourably adjus…
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UKAEA-CCFE-CP(21)042021
The use of small specimen test techniques (SSTT) to determine mechanical properties of irradiated materials has been studied over the previous decades both in fission and fusion programs, but also to characterise and optimise new materials by nuclear and non-nuclear communities. Currently a number of activities are running that focus on the standar…
Showing 1 - 10 of 19 UKAEA Paper Results