UKAEA Journals

Showing 1 - 8 of 8 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
2019
UKAEA-CCFE-PR(19)26

Guidelines are presented for the recommended method of assessing by analysis the structural integrity of divertor plasma facing components (PFCs) under high heat flux (HHF) loads. The objective is to enable analysis to provide greater supporting evidence for PFC qualification (which for ITER is currently achieved by test alone) and to provide reaso…

Preprint Purchase
The published version of this paper is currently under embargo and will be available on 21/06/2021
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
2017
CCFE-PR(17)53

Fusion demonstration (DEMO) concepts are facing challenges in safety and licensing in part due to uncertainties with in-vessel components validation, which relate directly to the materials and design criteria used for assessments. These challenges come from the designed operation under unprecedented environmental conditions and reliance on the perf…

Preprint Purchase
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
2014

Design optimization work has been conducted on the ITER Ion Cyclotron Resonance Heating (ICRH) Four Port Junction (4PJ) and Straps – a sub-assembly of the antenna. The aim of the analysis is to evaluate ways of making the component compliant with SDC-IC rules while balancing the competing demands of different performance requirements. Of particul…

Published