UKAEA Journals

Showing 1 - 10 of 11 Journals Results
2018
UKAEA-CCFE-PR(20)64

The JET outboard divertor targets are the in-vessel components which receive the largest heat flux density. Surface delamination, radial cracks, and tie rod failures have been observed in the outboard tungsten-coated CFC tiles, while bulk tungsten special lamellas were intentionally melted in dedicated experiments. These different types of damag…

Preprint
2018
UKAEA-CCFE-PR(18)39

Tungsten has long been the favoured armour material for plasma facing high heat flux components proposed for future fusion reactors, but studies examining the use of tungsten or other refractory metals in the underlying cooled structures have historically excluded them, leaving current concepts heavily dependent on copper alloys such as copper chro…

Preprint Published
2018
UKAEA-CCFE-PR(18)33

The development of improved designs for components which will be subject to high heat fluxes has been identified as a critical challenge for the realisation of commercial fusion power. This paper presents details of a facility which allows early verification of thermofluid and thermomechananical performance of prototype components and enables compa…

Preprint
2016
CCFE-PR(16)33

The microstructure and thermal stability of V-4Cr-4Ti-1.8Y-0.4Ti3SiC2 alloy, fabricated by 60 hr mechanical milling of blended powders followed by spark plasma sintering (SPS) and hot isostatic pressing, has been investigated. Analysis was undertaken using orientation image maps obtained from the electron backscattering and transmission Kikuchi dif…

Preprint Purchase
2016
CCFE-PR(16)59

The detachment of a beryllium tile from the ITER Normal Heat Flux (NHF) First Wall (FW) panels would result in an unacceptable degradation of panel performance. Such detachment has previously been observed under High Heat flux (HHF) testing of NHF FW prototypes, with initiation of de-bonding at tile edges and subsequent delamination occurring betwe…

Preprint
2016
CCFE-PR(16)60

The European ITER First Wall panel design relies on a HIP based manufacturing sequence. However, failures of the bond to the beryllium tile might occur during the fabrication and under high heat flux qualification. A dedicated project has been stablished between UKAEA/CCFE and F4E aiming to identify suitable repair techniques. One of the most prom…

Preprint
2014

The erosion and high neutron flux in a fusion power plant results in the need for frequent remote replacement of the plasma facing components. This is a complex and time consuming remote handling operation and its duration directly affects the availability and therefore the commercial viability of the power plant. A tool is needed to allow the main…

Published
2014

The need to populate the fusion materials engineering data base has long been recognized, the IFMIF facility being the present proposed neutron source for this purpose. Re-evaluation of the regulatory approach for the EU proposed DEMO device shows that the specification of the neutron source can be reduced with respect to IFMIF, allowing lower risk…

Published
2014

The materials engineering data base relevant to fusion irradiation is poorly populated and it has long been recognized that a fusion spectrum neutron source will be required, the facility IFMIF being the present proposal. Reevaluation of the regulatory approach for the EU proposed DEMO device shows that the purpose of the source can be changed from…

Published
2013

The materials engineering data base relevant to fusion irradiation is poorly populated and it has long been recognized that a fusion spectrum neutron source will be required, the facility IFMIF being the present proposal. Re-evaluation of the regulatory approach for the EU proposed DEMO device shows that the purpose of the source can be changed fro…

Published