A. Litnovsky F. Klein X. Tan J. Schmitz J. W. Coenen C. Linsmeier J. Gonzalez-Julian M. Bram I. Povstugar T. Morgan Y. M. Gasparyan A. Suchkov D. Bachurina D. Nguyen-Manh M. Gilbert D. Sobieraj J. S. Wróbel P. Bittner A. Reuban
Self-passivating Metal Alloys with Reduced Thermo-oxidation (SMART) are under development for the primary application as plasma-facing materials of the first wall in a fusion DEMOnstration power plant (DEMO). SMART materials must combine the suppressed oxidation in case of an accident and an acceptable plasma performance during the regular operatio…
Preprint PublishedK. Arakawa Z. Bergstrom M.J. Caturla S.L. Dudarev F. Gao M.R. Gilbert A.M. Goryaeva S.Y. Hu X. Hu R.J. Kurtz A. Litnovsky J. Marian M.-C. Marinica E. Martinez E.A. Marquis D.R. Mason B.N. Nguyen P. Olsson Y. Osetskiy D. Senor
Prediction of material performance in fusion reactor environments relies on computational modelling, and will continue to do so until the first generation of fusion power plants come on line and allow long-term behaviour to be observed. In the meantime, the modelling is supported by experiments that attempt to replicate some aspects of the eventua…
Preprint PublishedM. J. Lloyd A. J. London M. Gilbert C. S. Becquart C. Domain E. Martinez M. Moody P. A. J. Bagot D. Nguyen-Manh D.E. J. Armstrong
Tungsten is one the primary candidate materials for the high neutron flux, high temperature components of a future demonstrate fusion reactor. Despite this, there is a lack of data on W under fusion relevant neutron doses and irradiation temperatures. Transmutation reactions result in the production of Re and Os solute atoms, at a rate which is …
Preprint PublishedG.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 PublishedL. W. Packer P. Batistoni B. Colling K. Drozdowicz M. Fabbri Z. Ghani M. R Gilbert S. Jednorog E. Laszynska D. Leichtlef J.W.Mietelski C.R. Nobs M. Pillon I.E. Stamatelatos T. Vasilopoulou R. Villari A. Wójcik-Gargula JET Contributors
The planned high-profile experiments during 2020 at the Joint European Torus (JET), notably including a deuterium-tritium (DT) experimental phase, are expected to produce large neutron yields, in the region of 1021 neutrons. The scientific objectives are linked with a technology programme, WPJET3, to deliver the maximum scientific and…
PreprintJ.A.Bromley R.Vale M.R.GIlbert
The paper looks at a selective smelting regime where higher activity components are smelted with lower activity components with the aim to reduce the amount of ILW waste for disposal. This has been applied to the European DEMO Fusion Plant HCPB 2015 baseline design waste assessment. The paper assesses the structural steels in the breeder blanket…
PreprintC.R. Nobs L. W. Packer P. Batistoni B. Colling Z. Ghani M. Gilbert S. Loreti K. Mergia S. Mesoloras I. Michelakaki M. Pillon M. I. Savva I. E. Stamatelatos K. Triantou T. Vasilopoulou
In future fusion power plants, such as DEMO, D-T neutron emission is predicted to exceed 1×1021 neutrons/second. Accurately monitoring neutron energies and intensities will be the primary method for estimating fusion power, and calculating key parameters, including the tritium breeding ratio and nuclear heating. The Novel Neutron Det…
Preprint PublishedL. W. Packer S. Allan S. B. Bradnam M. R. Gilbert T. Stainer
The measurement of the fusion neutron yield provides a direct relationship with fusion power and is hence an important measure of experimental performance. In pulsed neutron emission scenarios, such as those experienced in dense plasma focus devices, inertial confinement fusion and even in short-pulse tokamak experiments, considerations of the dyna…
Preprint PublishedR. Worrall B. Colling M. R. Gilbert E. Litherland-Smith C. R. Nobs L. W. Packer C. Wilson A. Zohar
Spectrum unfolding is a key tool used together with diagnostics in the determination of nuclear fields that are associated with a range of nuclear technologies spanning fusion, fission, nuclear medicine and accelerator domains. The underlying process requires a mathematical method for solving the Fredholm integral equation of the first kind. This p…
Preprint PublishedP.D. Edmondson B. Gault M.R. Gilbert
Tungsten is the prime candidate material for the plasma facing divertor system and first wall armor of future nuclear fusion reactors. However, the understanding of the microstructural and chemical evolution of pure tungsten under neutron irradiation is relatively unknown, in part due to a lack of experimental data on this topic. Here, single cr…
Preprint Published