UKAEA Journals

Showing 1 - 10 of 45 Journals Results
2021
UKAEA-CCFE-PR(21)43

The chapter is devoted to materials used in controlled fusion facilities. Material solutions for magnetic confinement fusion devices and inertial confinement fusion facilities are described. Fusion materials have to preserve their performance often under extremely harsh conditions characterized by intensive particle fluxes, high levels of neutron i…

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The published version of this paper is currently under embargo and will be available on 23/06/2023
2021
UKAEA-CCFE-PR(21)42

Tungsten and tungsten alloys are being considered as leading candidates for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for the design of magnetic and inertial fusion energy reactors are its high melting point, high thermal conductivity, low sputtering yield and low long-term dispo…

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The published version of this paper is currently under embargo and will be available on 01/07/2022
2021
UKAEA-CCFE-PR(21)41

Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials of the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine the suppressed oxidation in case of an accident and an acceptable plasma performance during the regular operatio…

Preprint
2021
UKAEA-CCFE-PR(21)33

Prediction of material performance in fusion reactor environments relies on computational modelling, and will continue to do so until the first generation of fusion power plants come on line and allow long-term behaviour to be observed. In the meantime, the mode…

Preprint Published
The published version of this paper is currently under embargo and will be available on 08/06/2023
2021
UKAEA-CCFE-PR(21)27

Tungsten is one the primary candidate materials for the high neutron flux, high temperature components of a future demonstrate fusion reactor. Despite this, there is a lack of data on W under fusion relevant neutron doses and irradiation temperatures. Transmutation reactions result in the production of Re and Os solute atoms, at a rate which is …

Preprint
2020
UKAEA-CCFE-PR(21)18

During operation fusion reactor components will be exposed to long periods of neutron irradiation. As such, a reactor's structural steels will become activated and need to be disposed of as radioactive waste. Previous studies have shown that such wastes can struggle to meet low level waste requirements meaning that costly geological disposal may be…

Preprint Published
2020
UKAEA-CCFE-PR(20)115

Spectrum unfolding is a key tool used together with diagnostics in the determination of nuclear fields that are associated with a range of nuclear technologies spanning fusion, fission, nuclear medicine and accelerator domains. The underlying process requires a mathematical method for solving the Fredholm integral equation of the first kind. This p…

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The published version of this paper is currently under embargo and will be available on 19/10/2022
2020
UKAEA-CCFE-PR(20)109

Tungsten is the prime candidate material for the plasma facing divertor system and first wall armor of future nuclear fusion reactors. However, the understanding of the microstructural and chemical evolution of pure tungsten under neutron irradiation is relatively unknown, in part due to a lack of experimental data on this topic. Here, single cr…

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2020
UKAEA-CCFE-PR(20)78

During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first wall cladding may exceed 1000oC and remain for months leading to tungsten oxidation. The radioactive tungsten oxide can be mobilized to the environment at rates of 10 – 150 kg per hour. Smart tungsten-based alloys are under develop…

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2020
UKAEA-CCFE-PR(20)69

Molybdenum is a potential material for future nuclear fusion experiments and power plants. It has good thermo-mechanical properties and can be readily fabricated, making it attractive as an alternative material to tungsten (the current leading candidate) for high neutron flux and high thermal load regions of fusion devices. Unfortunately, exposu…

Preprint Published