Chris Hardie Rhys Thomas Yang Liu Philipp Frankel Fionn Dunne
Classical crystal plasticity formulation based on dislocation slip was extended to include the mechanisms of dislocation channelling, with associated strain softening which is observed in many alloys post irradiation. The performance of the model was evaluated against experimental data on Zircaloy-4, which included engineering stress-strain respons…
Preprint PublishedTay Sparks Duc Nguyen-Manh Pengfei Zheng Jan S. Wróbel Michael Gorley Thomas Connolley Christina Reinhard Yiqiang Wang Biao Cai
Vanadium base alloys represent potentially promising candidate structural materials for use in nuclear fusion reactors due to vanadium’s low activity, high thermal strength, and good swelling resistance. In this work, the mechanical properties of the current frontrunner vanadium base alloy, V-4Cr-4Ti, have been interrogated using in-situ high ene…
Preprint PurchaseMia Maric Rhys Thomas Tamas Ungar Gyula Zilahi Callum Hunt David Lunt Jack Donoghue Kieran Lynch Philipp Frankel Pierre Barberis Florent Bourlier Michael Preuss Pratheek Shanthraj
Hydride precipitation and reorientation has the potential to embrittle zirconium alloys. This study aims to better understand the influence of the Zr microstructure on hydride precipitation and reorientation. Specifically, the crystallography, phase stability and morphology of hydride precipitation was correlated to microstructural variations due t…
PreprintAlex Valentine Thomas Berry Steven Bradnam James Hagues James Hodson
The accurate and efficient mapping of the radiation environment in a nuclear fusion reactor requires the most advanced radiation transport tools. The Monte Carlo method has long been deployed to deal with the complexity of fusion relevant geometries, with MCNP the adopted industry standard code among the European and wider international community. …
PreprintA. Hollingsworth M.-F. Barthe M.Yu. Lavrentiev P.M. Derlet S.L. Dudarev D.R. Mason Z. Hub P. Desgardin J. Hess S. Davies B. Thomas H. Salter E.F.J. Shelton K. Heinolade K. Mizohatad A. De Backera A. Baron-Wiechec I. Jepuh Y. Zayachuka A. Widdowson E. Meslini A. Morelleci
Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simulating microstructures generated by neutron irradiation in tungsten components of a fusion reactor. Electron microscopy has been used to characterize defects formed in tungsten samples by ion irradiation and estimate their density and size distribution. Some of the sample…
Preprint PurchaseDaniel R. Mason Fredric Granberg Max Boleininger Thomas Schwarz-Selinger Kai Nordlund Sergei L. Dudarev
Hydrogen isotopes are retained in materials for fusion power applications, changing both hydrogen embrittlement and tritium inventory as the microstructure undergoes irradiation damage. But modelling of the highly damaged regime – over 0.1 displacements per atom (dpa) – where asymptotic saturation is observed, is difficult because a highly dama…
Preprint PurchaseJ. T. Parker P. A. Hill D. Dickinson B. D. Dudson
Tridiagonal matrix inversion is an important operation with many applications. It arises frequently in solving discretized one-dimensional elliptic partial differential equations, and forms the basis for many algorithms for block tridiagonal matrix inversion for discretized PDEs in higher-dimensions. In such systems, this operation is often the …
Preprint PurchaseThomas R. Barrett T. Grant M. Kovari N. Mantel A. Muir
Investment in past fusion experiments has been motivated largely by the study of tokamak physics, and has been vital to provide a sound physics basis for design of a power reactor. However, meeting the challenge of realising fusion energy production will require considerable and increasing investment in facilities for testing and development of fus…
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…
Preprint PublishedA. Hollingsworth M.-F. Barthe Z. Hu P. Desgardin M.Yu. Lavrentiev S.L. Dudarev P. Derlet D. Mason J. Hess S. Davies B. Thomas H. Salter E.F.J. Shelton K. Heinola K. Mizohata A. De Backer A. Baron-Wiechec I. Jepu E. Zayachuk A. Widdowson E. Meslin A. Morellec
Self-ion bombardment of pure tungsten with ion energies of 2 MeV is used to mimic the defects created by neutrons in a fusion reactor. Electron microscopy is used to characterize the microstructure of samples. Thermal Desorption Spectrometry (TDS) is performed on deuterium implanted samples in order to estimate deuterium inventory as function of…
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