E.R. Solano G. Birkenmeier C. Silva E. Delabie J.C. Hillesheim A. Baciero I. Balboa M. Baruzzo A. Boboc M. Brix C. Bourdelle I.S. Carvalho P. Carvalho C.D. Challis M. Chernyshova A. Chomiczewska R. Coelho T. Craciunescu E. de la Cal E. de la Luna R. Dumont P. Dumortier M. Fontana J.M. Fontdecaba L. Frassinetti D. Gallart J. Garcia C. Giroud W. Gromelski R.B. Henriques J. Hall A. Ho L. Horvath P. Jacquet I. Jepu E. Joffrin A. Kappatou P.J. Lomas D.L. Keeling D.B. King E. Kowalska-Strzęciwilk M. Lennholm E. Lerche E. Litherland-Smith V.G. Kiptily K.K. Kirov A. Loarte B. Lomanowski C.F. Maggi J. Mailloux M.J. Mantsinen M. Maslov A.G. Meigs I. Monakhov R.B. Morales A.H. Nielsen D. Nina C. Noble E. Pawelec M. Poradzinski G. Pucella P. Puglia D. Réfy J.J. Rasmussen E. Righi-Steele F.G. Rimini T. Robinson M. Sertoli S.A. Silburn P. Sirén Ž. Štancar H.J. Sun G. Szepesi D. Taylor B. Thomas E. Tholerus G. Verdoolaege P. Vincenzi B. Viola N. Vianello T. Wilson
Preprint Published
D. Lunt R. Thomas D. Bowden M. T. P. Rigby-Bell S. de Moraes Shubeita C. Andrews T. Lapauw J. Vleugels J. Quinta da Fonseca K. Lambrinou P. Frankel
Materials subjected to irradiation damage often undergo local changes in the microstructure that effect the expected performance. To investigate those changes, this work proposes a novel approach to detect strain localisation caused by irradiation-induced damage in nuclear materials on the microstructural level, conside…
PublishedThomas Stokes Mirjana Damjanovic Joe Berriman Stephen Reynolds
Investigations were undertaken into the thermal treatment of beryllium and tungsten to see if these materials can be detritiated in the Material Detritiation Facility (MDF) at UKAEA, allowing for the declassification of intermediate level waste (ILW) to low level waste (LLW). When heated in oxygen, both tungsten and beryllium readily oxidise, wi…
Preprint PublishedR. Thomas Ö. Koç T. Ungar G. Zilahi H. Xu Z. Hegedues U. Lienert G. Ribarik H. Sharma P. Kenesei M. Preuss P. Frankel
During operation, structural components made of zirconium alloys are subject to neutron irradiation, which leads to the displacement of zirconium atoms from their lattice sites, the production of self-interstitials and vacancies, and eventually dislocation loops. This process can lead to deleterious effects such as irradiation growth, creep and …
Preprint PurchaseR. Thomas D. Bowden D. Lunt D. Stewart M. Preuss
Hard-facing alloys in nuclear applications must remain resistant to deformation and wear, whilst also minimising transmutation to problematic elements during service. To this end, the Fe-based alloy RR2450 has been developed to potentially replace Co-based hard-facing alloys. RR2450 is a complex multi-phase stainless steel alloy showing an unusuall…
PreprintM.Yu. Lavrentiev A. Hollingsworth J. Hess S. Davies A. Wohlers B. Thomas H.Salter A. Baron-Wiechec I. Jepu Y. Zayachuk N. Peng
Molybdenum is used as plasma-facing material in tokamaks and as material for plasma optical diagnostic mirrors. Harsh conditions of neutron irradiation, exposure to hydrogen isotopes and helium, and high temperature result in degradation of molybdenum surface and ultimately limit the lifetime of fusion power plant. In the current paper, we inves…
PreprintChris 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 PublishedMia 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…
Preprint PurchaseAlex 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. …
Preprint