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Defect accumulation and evolution during prolonged irradiation of Fe and FeCr alloys
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The correlation of indentation experiments
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Primary radiation damage: A review of current understanding and models
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On the use of ion beams to emulate the neutron irradiation behaviour of tungsten
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Digital autofocusing of a coded-aperture Laue diffraction microscope
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Microstructure of neutron-irradiated iron before and after tensile deformation
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October 2021 |
On the correlation between self-interstitial cluster diffusivity and irradiation-induced swelling in Fe–Cr alloys
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Small-scale characterisation of irradiated nuclear materials: Part II nanoindentation and micro-cantilever testing of ion irradiated nuclear materials
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Dose dependence of defect accumulation in neutron irradiated copper and iron
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Effect of chromium on void swelling in ion irradiated high purity Fe–Cr alloys
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April 2016 |
Influence of carbon on the evolution of irradiation defects in tungsten
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Eeffect of fast-neutron irradiation on mechanical properties of iron and some iron binary solid solutions
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Ab initio study of Cr interactions with point defects in bcc Fe
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Defect structures and statistics in overlapping cascade damage in fusion-relevant bcc metals
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A proposed method of calculating displacement dose rates
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Ion-irradiation-induced damage in Fe–Cr alloys characterized by nanoindentation
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Aspects of simulation of neutron damage by ion irradiation
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Nanoindentation on ion irradiated steels
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Microstructure and nanoindentation of the CLAM steel with nanocrystalline grains under Xe irradiation
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He and Cr effects on radiation damage formation in ion-irradiated pure iron and Fe–5.40wt.% Cr: A transmission electron microscopy study
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On the origin of primary ½ a0 <111> and a0 <100> loops in irradiated Fe(Cr) alloys
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July 2017 |
Relaxation volumes of microscopic and mesoscopic irradiation-induced defects in tungsten
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Interstitials and Vacancies in α Iron
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Nanoindentation of model Fe–Cr alloys with self-ion irradiation
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Multiscale modelling of radiation damage and phase transformations: The challenge of FeCr alloys
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Materials research for fusion
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Lattice swelling and modulus change in a helium-implanted tungsten alloy: X-ray micro-diffraction, surface acoustic wave measurements, and multiscale modelling
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Forced flow cryogenic cooling in fusion devices: A review
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Self-interstitial atom defects in bcc transition metals: Group-specific trends
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Detection of one-dimensional migration of single self-interstitial atoms in tungsten using high-voltage electron microscopy
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Three-dimensional X-ray structural microscopy with submicrometre resolution
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Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys
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August 2013 |
Development of benchmark reduced activation ferritic/martensitic steels for fusion energy applications
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The effect of orientation and temperature on the plastic flow properties of iron single crystals
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Void-swelling in irons and ferritic steels
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Computer simulation study of cascade overlap effects in α-iron
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Characterising Ion-Irradiated FeCr: Hardness, Thermal Diffusivity and Lattice Strain
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Effects of chromium on the one-dimensional motion of interstitial-type dislocation loops in iron
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Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 2: Damage evolution in thin-foils at higher doses
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July 2008 |
Observation of Transient and Asymptotic Driven Structural States of Tungsten Exposed to Radiation
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Direct observation of size scaling and elastic interaction between nano-scale defects in collision cascades
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The influence of carbon impurities on the formation of loops in tungsten irradiated with self-ions
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A TEM study of neutron-irradiated iron
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Void swelling in binary FeCr alloys at 200 dpa
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Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy
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Structural materials for fission & fusion energy
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Thermal diffusivity degradation and point defect density in self-ion implanted tungsten
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July 2020 |
Compositional and temperature dependence of void swelling in model Fe–Cr base alloys irradiated in the EBR-II fast reactor
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Nanoindentation Response of Ion-Irradiated Fe, Fe-Cr Alloys and Ferritic-Martensitic Steel Eurofer 97: The Effect of Ion Energy
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On the use of SRIM for computing radiation damage exposure
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Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses
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July 2008 |
Mechanical properties and plasticity size effect of Fe-6%Cr irradiated by Fe ions and by neutrons
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December 2016 |
Helium-implantation-induced lattice strains and defects in tungsten probed by X-ray micro-diffraction
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December 2018 |
Microstructural examination of neutron-irradiated simple ferritic alloys
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July 1982 |
Simulations of weak-beam diffraction contrast images of dislocation loops by the many-beam Howie–Basinski equations
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A multi-scale model for stresses, strains and swelling of reactor components under irradiation
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September 2018 |
A new approach to evaluate irradiation hardening of ion-irradiated ferritic alloys by nano-indentation techniques
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Molecular dynamics simulation of displacement cascades in α-Fe: A critical review
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Challenges to the use of ion irradiation for emulating reactor irradiation
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April 2015 |
Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
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On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options
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September 2021 |