UKAEA Journals

Showing 1 - 9 of 9 Journals Results
2019
UKAEA-CCFE-PR(20)98

A high performing DEMO divertor target mock-up design that uses the thermal break interlayer concept is presented.  The design evolved from a previous design of which six mock-ups were designed, fabricated and subjected to high heat flux testing.  The new design was generated using optimisation techniques; specifically, software was developed …

Preprint Purchase
2018
UKAEA-CCFE-PR(18)53

Within a tokamak fusion energy device, the performance and lifespan of a divertor monoblock under high heat flux cycles is of particular interest. Key to this is the quality of manufacture, especially the material joining interfaces. Presented here is a comparative study between X-ray and neutron tomography to investigate the quality of manufacture…

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
2015
CCFE-PR(17)26

For the initial phase of MAST-U operation the two existing neutral beam injection systems will be used, but must be substantially upgraded to fulfil expected operational requirements. The major elements are the design, manufacture and installation of a bespoke bending magnet and Residual Ion Dump (RID) system. The MAST-design full energy dump is b…

Preprint Published
2015
CCFE-PR(15)117

The phenomenon of redistribution of neutral beam fast-ions due to MHD activity in plasma has been observed on many tokamaks and more recently has been a focus of research on MAST ( Turnyanskiy M. et al, 2013 Nucl. Fusion 53 053016 ). n=1 fishbone modes are observed to cause a large decrease in the neutron emission rate indicating to exist a signifi…

Preprint Published
2015

HyperVapotrons are two-phase water-cooled heat exchangers able to receive high heat fluxes (HHF) byemploying a cyclic phenomenon called the "Vapotron Effect". HyperVapotrons have been used routinelyin HHF nuclear fusion applications. A detailed experimental investigation on the effect giving rise to theability to sustain steady state heat fluxes in…

Published
2013

The thermal performance of high heat flux components in a fusion reactor could be enhanced significantly by the use of nanofluid coolants, suspensions of a liquid with low concentrations of solid nanoparticles. However, before they are considered viable for fusion, the long-term behaviour of nanofluids must be investigated. This paper reports an ex…

Published