M. Tindall T. Deighan S. Rosini N. Bowden S. Biggs-Fox T. Barrett
Critical to the successful design of fusion reactor components is the development of coupled simulation models, capable of conducting efficient whole system design optimisation and virtual component qualification, under conditions which cannot be readily tested. Additionally, successful lifetime monitoring and predictive maintenance of fusion compo…
Preprint PublishedN. Mantel D. Bowden S.S. Herashchenko M. Fursdon A. D. L. Hancock I.E. Garkusha J. Roberts V.A. Makhlai A. von Mueller T. R. Barrett J.-H. You
In the conceptual design of EU-DEMO, damage to plasma facing components under disruption events is planned to be mitigated by specific sacrificial limiter components. A new limiter concept has been proposed using lattice structures fabricated with tungsten powder by additive manufacturing techniques. The major potential benefits of using a latti…
Preprint PublishedF. Schoofs A. Cackett J. Lim S. M. King A. Schiavi T. R. Barrett C. Hardie
The divertor component is subject to some of the most extreme loading conditions in a fusion environment and the safety design window is relatively narrow. Variation in mechanical properties of the same material throughout a component is common place in practice and can be caused by both local effects of processing and joining, and local variations…
Preprint PublishedK Flinders R Bamber H Lewtas D Hancock D Homfray J Kamalu T Barrett
High heat flux testing is a vital part of engineering component validation for fusion technology. Typically, it is an expensive process that is both time and resource intensive. The Heat by Induction to Verify Extremes (HIVE) facility is designed to improve the practicalities of this form of component testing. It provides a faster turnaround for…
Preprint PublishedF. Domptail T.R. Barrett M. Fursdon A. Lukenskas J-H. You
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 to …
Preprint PublishedThomas R. Barrett T. Grant M. Kovari N. Mantel A. Muir
Investment in past fusion experiments has been motivated largely by the study of tokamak physics, and has been vital to provide a sound physics basis for design of a power reactor. However, meeting the challenge of realising fusion energy production will require considerable and increasing investment in facilities for testing and development of fus…
Preprint PublishedZ. Vizvary W. Arter C. Bachmann T. R. Barrett B. Chuilon P. Cooper M. Firdaouss T. Franke J. Gerardin R. Gowland M. Kovari F. Maviglia L. M. Richiusa E. V. Rosa Adame C. Vorpahl A. Wilde Y. Xue
The anticipated heat flux limit of the European DEMO first wall is ~1MW/m2. During transient and off normal events, the heat load deposited on the wall would be much larger than that the steady state heat load and exceed the first wall limit, therefore the breeding blanket first wall needs to be protected in such events. This involves de…
Preprint PublishedZ. Vizvary W. Arter T. R. Barrett D. Calleja M. Firdaouss J. Gerardin M. Kovari F. Maviglia L. Richiusa
Within the DEMO first wall 3-D shape design activity the first study of the effect of misalignment has started. Such assessments have been conducted in the past for ITER and penalty factor maps have been created; this route could be a feasible approach in the case of DEMO wall design also. This paper details the first set of computational tests tha…
Preprint PublishedLlion M. Evans T. Minniti T. Barrett A. von Muller L. Margetts
This paper presents the application of the image-based finite element method (IBFEM) to quantify the impact of micro-structure caused by manufacturing processes on the performance of fusion energy heat exchangers. The components, containing tungsten, were imaged with high-power lab-based X-ray CT and neutron CT. Volume data was converted into part-…
Preprint PublishedLlion Evans T. Minniti M. Fursdon M. Gorley T. Barrett F. Domptail E. Surrey W. Kockelmann A.v. Müller F. Escourbiac A. Durocher
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- 1
- 2