L. W. Packer P. Batistoni N. Bekris S. C. Bradnam H. Chohan M. Fabbri Z. Ghani M. R. Gilbert R. Kierepko E. Laszynska D. Leichtle I. Lengarf S. Loreti J. W. Mietelski C. R. Nobs M. Pillon M. I. Savva I. E.Stamatelatos T. Vasilopoulou A. Wojcik-Gargula A. Zoharf JET Contributors
The characteristically intense neutron source generated in deuterium-tritium (DT) fusion power presents notable challenges for materials comprising the structure of the device which are exposed to them. These include radiation damage effects leading to degradation of structural properties with impact on maintenance and replacement frequency, but…
PreprintEnrique Miralles-Dolz Alexander Pearce James Morris Edoardo Patelli
To make informed decisions during the concept selection activities of a fusion power plant it is necessary to evaluate the impact of uncertainties on the feasibility and performance of each concept. A framework for uncertainty quantification and sensitivity analysis has been developed for the PROCESS systems code to allow the direct comparison o…
PreprintA.J. Pearce S. Kahn J. Morris S.I. Muldrew
Conceptual designs for a European demonstration power plant (EU-DEMO) are based on extrapolations of physics scaling laws and current understanding of engineering limits based on available technologies. It is imperative to quantify the impact of uncertainties in physics and engineering parameters on the ability to produce an economically attract…
PreprintS. Omole A. J. G. Lunt S. Kirk A. Shokrania
The high ductile-to-brittle transition temperature (DBTT) of tungsten combined with its high hardness make machining incredibly difficult. These properties typically result in the poor-quality machined surfaces and short tool life. In this study, TiAlN coated carbide tools with different rake angles (8°, 10° and 12°) were tested in convention…
PreprintJ. R. Echols L. M. Garrison N. Reid C. M. Parish D. Morrall A. Hasegawa A. Bhattacharya Y. Katoh
A major challenge for heat transfer in nuclear materials is to ensure thermal mobility after high amounts of neutron irradiation. Tungsten is widely selected as a heat transfer material in fusion reactors. In metals, thermal conductivity is dominated by electrons’ ability to transfer energy. Neutron irradiation generates point defects, c…
Preprint PublishedTristan Calvet Yiqiang Wang Minh-Son Pham Catrin Davies
Sandwich-type cooling pipes of the first wall of future fusion nuclear reactors (i.e. DEMO) will likely consist of tungsten brazed to a Reduced Activation Ferritic Martensitic (RAFM) steel. Under a high heat flux (HHF) (1-5 MW/m2) the mismatch in thermal expansion between tungsten and steel results in significant thermal stresses in the brazing …
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. Naish P. Batistoni B. Kros B. Obryk R. Villari JET contributors
In 2019 JET carried out a very successful Deuterium-Deuterium campaign, referred to as C38, producing a total of 3.751019 DD neutrons. During this campaign, a series of experiments were implemented to record the neutron fluence at positions close and far from the source and along shielding penetrations. Measurements were performed usi…
PreprintD. Kumar J. Hargreaves A. Bharj A. Scorror L. M. Harding H. Dominguez-Andrade R. Holmes R. Burrows H. Dawson A. D. Warren P.E.J. Flewitt T.L. Martin
Plasma-wall interactions in a commercial-scale fusion power station may exert high transient thermal loads on plasma-facing surfaces, repeatedly subjecting underlying structural materials to high temperatures for short durations. Specimens of the reduced activation ferritic-martensitic steel Eurofer-97 were continuously aged at constant temperat…
Preprint PublishedOlga Vilkhivskaya Mark Gilbert
Recent studies of the neutron irradiation conditions predicted in the plasma-exposed first wall of a conceptual design of fusion DEMO power plant implementing the SPECTRA-PKA code have shown the importance of taking into consideration per-channel analysis of the high-energy threshold reactions for an accurate evaluation of their contribution to …
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