Elena V. Rosa Adame Andrius Aleksa Mark R. Gilbert Martin Cuddy Tristan Calvet Zsolt Vizvary Nicolas Mantel Francesco Maviglia Jeong Ha You
A development plan for validation of functional principles is defined to support the challenges of mock-up manufacturing and testing. It is aimed to develop the process and infrastructure for qualifying fusion components for the limiters in the European DEMO. The limiters are components that define the plasma boundary by direct contact during norma…
Preprint PublishedA. Litnovsky I. Duran J.W. Coenen Yu. Gasparyan M.R. Gilbert E. Hollmann Ch. Linsmeier S. Nogami C.H. Skinner S. Zinkle
The chapter is devoted to materials used in controlled fusion facilities. Material solutions for magnetic confinement fusion devices and inertial confinement fusion facilities are described. Fusion materials have to preserve their performance often under extremely harsh conditions characterized by intensive particle fluxes, high levels of neutron i…
PublishedYichen Qian Mark Gilbert Lucile Dezerald David Cereceda
Tungsten and tungsten alloys are being considered as leading candidates for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for the design of magnetic and inertial fusion energy reactors are its high melting point, high thermal conductivity, low sputtering yield and low long-term di…
Preprint PublishedA. 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 Published