All Papers - UKAEA Scientific Publications

Showing 1 - 10 of 29 UKAEA Paper Results

UKAEA-CCFE-PR(23)1802023

"L-H transition studies in recent Tritium and Deuterium-Tritium campaigns at JET"
- 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
UKAEA-CCFE-CP(24)072022

"Shutdown dose rates in-cryostat outside the EU-DEMO vacuum vessel"
Future fusion reactors using deuterium-tritium fuel will create high fluences of high-energy neutrons inside and around the reactor vessel. As well as causing material damage, fusion neutrons will activate materials, the decay of which leads to radiation fields in and around the reactor after shutdown. Gamma-ray emission from activated materials…
- Published
UKAEA-CCFE-PR(23)1492022

"Detecting irradiation-induced strain localisation on the microstructural level by means of high-resolution digital image correlation"
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…
- Published
UKAEA-CCFE-CP(23)592022

"Detritiation of JET Beryllium and Tungsten"
- Thomas 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
- Published
UKAEA-CCFE-PR(23)1342022

"Characterisation of irradiation damage using x-ray diffraction line profile analysis"
- R. 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
- Purchase
UKAEA-CCFE-PR(23)1332022

"High compressive loading performance of a complex multi-phase hard-facing alloy explained through a super-elastic silicide phase"
- R. 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…
- Preprint
UKAEA-CCFE-PR(23)1062022

"Effects of Self-Irradiation on Deuterium Retention and Reflectivity of Molybdenum, Fusion Plasma-Facing Material: Combined Experimental and Modelling Study"
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…
- Preprint
UKAEA-CCFE-PR(22)632022

"Simulation of Crystal Plasticity in Irradiated Metals: A Case Study on Zircaloy-4"
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
- Published
UKAEA-CCFE-PR(22)322022

"Mechanical Characterisation of V-4Cr-4Ti Alloy: Tensile Tests Under High Energy Synchrotron Diffraction"
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
- Published
UKAEA-CCFE-PR(22)252022

"CHARACTERISATION OF HYDRIDE PRECIPITATION AND REORIENTATION IN ZIRCONIUM ALLOYS AT DIFFERENT METALLURGICAL STATES"
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
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"L-H transition studies in recent Tritium and Deuterium-Tritium campaigns at JET"

"Shutdown dose rates in-cryostat outside the EU-DEMO vacuum vessel"

"Detecting irradiation-induced strain localisation on the microstructural level by means of high-resolution digital image correlation"

"Detritiation of JET Beryllium and Tungsten"

"Characterisation of irradiation damage using x-ray diffraction line profile analysis"

"High compressive loading performance of a complex multi-phase hard-facing alloy explained through a super-elastic silicide phase"

"Effects of Self-Irradiation on Deuterium Retention and Reflectivity of Molybdenum, Fusion Plasma-Facing Material: Combined Experimental and Modelling Study"

"Simulation of Crystal Plasticity in Irradiated Metals: A Case Study on Zircaloy-4"

"Mechanical Characterisation of V-4Cr-4Ti Alloy: Tensile Tests Under High Energy Synchrotron Diffraction"

"CHARACTERISATION OF HYDRIDE PRECIPITATION AND REORIENTATION IN ZIRCONIUM ALLOYS AT DIFFERENT METALLURGICAL STATES"

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