UKAEA Journals

Showing 1 - 10 of 49 Journals Results
2021
UKAEA-CCFE-PR(21)83

This Review considers current Zr alloys and opportunities for advanced zirconium alloys to meet the demands of a structural material in fusion reactors. Zr based materials in the breeder blanket offer the potential to increase the tritium breeding ratio above that of Fe, Si and V based materials. Current commercial Zr alloys might be considered …

Preprint Published
2021
UKAEA-CCFE-PR(21)68

Using the notion of eigenstrain produced by the defects formed in a material exposed to high energy neutron irradiation, we develop a method for computing macroscopic elastic stress and strain arising in components of a fusion power plant during operation. In a microstructurally isotropic material, the primary cause of macroscopic elastic stress an…

Preprint
2021
UKAEA-CCFE-PR(21)53

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…

Preprint Purchase
2021
UKAEA-CCFE-PR(21)51

A development plan for validation of functional principles is defined to support the challenges of mock-up manufacturing and testing. It is aimed to develop the process and infrastructure for qualifying fusion components for the limiters in the European DEMO. The limiters are components that define the plasma boundary by direct contact during norma…

Preprint
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 Published
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 modelling is supported by experiments that attempt to replicate some aspects of the eventua…

Preprint Published
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
2021
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