Shu Huang Ryan Kerr Samuel Murphy Mark R. Gilbert Jaime Marian
We present a numerical model to predict oxide scale growth on tungsten surfaces under exposure to oxygen at high temperatures. The model captures the formation of four thermodynamically-compatible oxide sublayers, WO2, WO2.72, WO2.9, and WO3, on top of the metal substrate. Oxide layer growth is simulated by tracking the oxide/oxide and oxide/metal …
PreprintYichen Qian Mark R. Gilbert Lucile Dezerald Duc Nguyen-Manh David Cereceda
Tungsten (W) is considered a leading candidate for structural and functional materials in future fusion energy devices. The most attractive properties of tungsten for magnetic and inertial fusion energy reactors are its high melting point, high thermal conductivity, low sputtering yield, and low long-term disposal radioactive footprint. However, t…
Preprint PublishedS. Von Tiedemann D Collins M. Gilbert I. Kodeli
Predictions of material activity in commercial fusion conditions predominantly rely on computational methods, due to a lack of data on long-term e ects of high-energy neutron irradiation on structural steels. Consequently, this could result in a bias due to uncertainties in nu…
Preprint PublishedMegha Sanjeeva Mark R. Gilbert Samuel T. Murphy
The transfer of heat through the breeder region of a future fusion reactor is a key component of its thermal efficiency. Development of advanced ceramic breeder materials based on Li2TiO3 seek to exploit its ability to accommodate significant non-stochiometry, however, it is not clear how deviations for the 50:50 mix of Li2O and TiO2 will affect…
PreprintSehila M. Gonzalez de Vicente Nicholas A. Smith Laila El-Guebaly Sergio Ciattaglia Luigi Di Pace Mark Gilbert Robert Mandoki Sandrine Rosanvallon Youji Someya Kenji Tobita David Torcy
In the absence of official standards and guidelines for nuclear fusion plants, fusion designers adopted, as far as possible, well-established standards for fission-based nuclear power plants (NPPs). This often implies interpretation and/or extrapolation, due to differences in structures, systems and components, materials, safety mitigation systems,…
Preprint PublishedL. 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…
PreprintMark R. Gilbert Greg W. Bailey
Accurate predictions of the severity and quantities of radioactive waste is an important part of the design, modelling, and engineering process of future fusion reactors. While fusion will not generate the same highly active spent fuel waste as fission, it will nonetheless create significant radioactive waste due to the interaction of neutrons w…
PreprintG.W. Bailey M.R. Gilbert T.A. Berry T. Eade C. Bachmann U. Fischer
Previous studies of the European Demonstration fusion reactor concept (DEMO) have shown that the expected amounts of radioactive waste at end of life (EOL) are of the order of 104 tonnes. These studies also suggested that comparable amounts of waste will be classified as low level waste (LLW) and intermediate level waste (ILW) 100 yea…
PreprintDamian Sobieraj Jan S. Wróbel Mark R. Gilbert Andrey Litnovsky Felix Klein Krzysztof J. Kurzydłowski Duc Nguyen-Manh
W-Cr-Y smart alloys are potential material candidates for plasma facing components due to their protective behaviour during the loss-of-coolant accident (LOCA), while maintaining beneficial properties of W during the normal operation of the fusion power plant. During plasma exposure the lighter alloying elements are preferentially sputtered at t…
PreprintD.J.M. King A.J. Knowles D. Bowden M.R. Wenman S. Capp M. Gorley J. Shimwell L. Packer M.R. Gilbert A. Harte
This Review considers current Zr alloys and opportunities for advanced zirconium alloys to meet the demands of a structural material in fusion reactors. Zr based materials in the breeder blanket offer the potential to increase the tritium breeding ratio above that of Fe, Si and V based materials. Current commercial Zr alloys might be considered …
Preprint Published