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 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 PublishedMark 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…
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…
PreprintMegha Sanjeev Mark R. Gilbert Samuel T. Murphy
The high anisotropy in the thermal conductivity of lithium metatitanate, Li2TiO3, is shown using the classical simulation method of Molecular Dynamics (MD). The thermal conductivity along the z-direction is markedly lower than that in x and y. This characteristic could be exploited to favourably adjus…
Preprint PurchaseElena 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…
PreprintYichen 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 dispo…
Preprint PublishedAndrey Litnovsky Janina Schmitza Felix Klein Karen De Lannoyea Sophie Weckauf Arkadi Kreter Marcin Rasinski Jan W. Coenen Christian Linsmeier Jesus Gonzalez-Julian Martin Bram Ivan Povstugar Thomas Morgan Duc Nguyen-Manh Mark Gilbert Damjan Sobieraj Jan S. Wróbel
During an accident with loss-of-coolant and air ingress in DEMO, the temperature of tungsten first wall cladding may exceed 1000oC and remain for months leading to tungsten oxidation. The radioactive tungsten oxide can be mobilized to the environment at rates of 10 – 150 kg per hour. Smart tungsten-based alloys are under develop…
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