G.W. Bailey O.V. Vilkhivskaya M.R. Gilbert
During operation fusion reactor components will be exposed to long periods of neutron irradiation. As such, a reactor's structural steels will become activated and need to be disposed of as radioactive waste. Previous studies have shown that such wastes can struggle to meet low level waste requirements meaning that costly geological disposal may be…
Preprint PublishedT. A. Berry C. R. Nobs A. Dubas R. Worrall T. Eade J. Naish L. W. Packer
The accurate modelling of the activation of flowing material in a fusion reactor, such as coolant water or lithium-lead breeder, has important safety and shielding implications. Two codes developed at UKAEA which account for neutron flux variation have been investigated for the potential for incorporating computational fluid dynamics (CFD) and c…
Preprint PublishedDavid Andres Marta Serrano Rebeca Hernandez Yiqiang Wang Mark Richardson
The use of small specimen test techniques (SSTT) to determine mechanical properties of irradiated materials has been studied over the previous decades both in fission and fusion programs, but also to characterise and optimise new materials by nuclear and non-nuclear communities. Currently a number of activities are running that focus on the standar…
PreprintJ. Keep T. Berry S. Budden B. Chuilon B. Colling E. Flynn S. Ha C. Jackson G. Keech W. Leong G. Mathew E. Organ C. Shaw A. Wilde
DEMO is a key part of the EU fusion roadmap, and the programme reaches the end of the pre-conceptual phase with a gate review in 2020. As part of the work to complete this phase, eight Key Design Integration Issues (KDII’s) have been identified as critical to the programme. Two of these KDII’s identified a requirement for a more detailed archit…
Preprint PublishedA.Valentine N.Fonnesu B.Bienkowska E.Laszynska D.Flammini R.Villari G.Mariano T.Eade T.Berry L.Packer
As a demonstration fusion power plant, EU DEMO has to prove the maturity of fusion technology and its viability for electricity production. The central requirements for DEMO rest on its capability to generate significant net electric power to the grid (300MW to 500 MW) safely and consistently. Plant availability and lifetime will approach that of a…
Preprint PublishedM. Richardson M. Gorley Y. Wang D. Andres H. Dawson
Small punch creep (SPC) testing represents an effective way to rapidly assess the creep performance of novel materials and potentially monitor degradation of in-service components. Recent progress in standardisation has also led to improvements in data analysis. However, estimation of equivalent uniaxial stresses is still somewhat challenging and h…
Preprint PublishedTriestino Minniti Frank Schoofs Llion Marc Evans Winfried Kockelmann J.H. You Heather Lewtas
The divertor target plates are the most exposed in-vessel components to high heat flux loads in a fusion reactor due to a combination of plasma bombardment, radiation and nuclear heating. Reliable exhaust systems of such a huge thermal power required a robust and durable divertor target with a sufficiently large heat removal capability and lifetime…
Preprint PublishedM. Coleman S. McIntosh J. Shimwell A. Davis
The creation of 3-D CAD models is one of the key steps in the fusion reactor design cycle, and is very much a recurring process. A common division of labour sees engineers, draughtspeople, and analysts iterate ideas, requirements and constraints, 3-D CAD model(s), and analyses, respectively, to iteratively converge upon a working design. Whilst thi…
Preprint PublishedM. Gorley G. Aiello J. Henry T. Nozawa G. Pintsuk M. Rieth H. Tanigawa
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…
Preprint PublishedH. Chohan M. Fabbri R. Pampin A. Portone G. D’Amico Á. Cubí
Finite element analysis (FEA) is widely used in engineering to accurately model physical systems. FEA enables multi-physics investigations to be undertaken efficiently and increases the cohesiveness of interdisciplinary engineering assessments. Thanks to the recent implementation of the FEA Unstructured Mesh capability (UM) into MCNP6, radiation tr…
Preprint Published