UKAEA Journals

Showing 1 - 8 of 8 Journals Results
2020
UKAEA-CCFE-PR(21)06

This work addresses an overview of the recent progress, associated risks and development plans of structural materials for in-vessel components (IVCs) in DEMO plants. Reduced Activation Ferritic Martensitic Steels form the primary structural materials for most DEMOs IVCs and will be the focus of the paper.   An overview of EU- and J-DEMO…

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The published version of this paper is currently under embargo and will be available on 23/03/2023
2020
UKAEA-CCFE-PR(20)112

A technology readiness assessment has been carried out on materials under development within the EUROfusion materials work package (WPMAT). This covers materials for structural, high heat flux and functional applications (breeder materials and coatings are not covered). The baseline materials have been assigned Material Technology Readiness Levels …

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The published version of this paper is currently under embargo and will be available on 27/02/2023
2019
UKAEA-CCFE-PR(19)51

Only limited data exist on the effect of neutron irradiation on the brittle to ductile transition (BDT) in tungsten. This work investigates the increase in brittle to ductile transition temperature (BDTT) following neutron irradiation to 1.67 displacements per atom, using four-point bend tests over a range of temperatures (623 – 1173 K) and strai…

Preprint Published
2018
UKAEA-CCFE-PR(18)63

The current paper reports the work of the EUROfusion Material Database and Handbook group within the MAT-EDDI (Materials – Engineering Data and Design Integration) subproject of the EUROfusion consortium. A special emphasis is put on the building of the EUROfusion RAFM steel database accounting around 3000 raw materials data records. A dat…

Preprint Published
2016
CCFE-PR(16)03

The European DEMO power reactor is currently under conceptual design within the EUROfusion Consortium. One of the most critical activities is the engineering of the plasma-facing components (PFCs) covering the plasma chamber wall, which must operate reliably in an extreme environment of neutron irradiation and surface heat and particle flux, while …

Preprint Published
2015
CCFE-PR(17)21

A robust water-cooled divertor target plate solution for DEMO has to date remained elusive. Common to all contemporary concepts is an interlayer at the boundary between the tungsten armour and the cooling structure. In this paper we show by design optimisation that an effectively designed interlayer can produce dramatic gains in power handling. By …

Preprint Published
2015
CCFE-PR(17)29

The design of a divertor target for DEMO remains one of the most challenging engineering tasks to be overcome on the path to fusion power. Under the European DEMO programme, a promising concept known as Thermal Break has been developed at CCFE. This concept is a variation of the ITER tungsten divertor in which the pure Copper interlayer between Cop…

Preprint Published