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High temperature annealing of ion irradiated tungsten

Acta materialia, 2015-05, Vol.90, p.380-393

2015

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Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys

Acta materialia, 2018-02, Vol.144, p.716-727

2018

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The effect of electronic energy loss on irradiation-induced grain growth in nanocrystalline oxides

Physical chemistry chemical physics : PCCP, 2014-01, Vol.16 (17), p.851-859

2014

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Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys

Journal of nuclear materials, 2018-12, Vol.512 (C), p.227-238

2018

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Site specific, high-resolution characterisation of porosity in graphite using FIB-SEM tomography

Journal of nuclear materials, 2018-12, Vol.511 (C), p.164-173

2018

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Radiation induced amorphization of carbides in additively manufactured and conventional ferritic-martensitic steels: In-situ experiments on extraction replicas

Journal of nuclear materials, 2022-05, Vol.563 (C), p.153646, Article 153646

2022

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Development of mesopores in superfine grain graphite neutron-irradiated at high fluence

Carbon (New York), 2019-01, Vol.141 (C), p.663-675

2019

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Nanoprecipitates to Enhance Radiation Tolerance in High-Entropy Alloys

ACS applied materials & interfaces, 2023-01, Vol.15 (3), p.3912-3924

2023

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Microstructural investigation of an extruded austenitic oxide dispersion strengthened steel containing a carbon-containing process control agent

Journal of nuclear materials, 2019-04, Vol.516 (C), p.335-346

2019

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Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

Journal of nuclear materials, 2021-06, Vol.549 (1), p.152804, Article 152804

2021

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The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys

Journal of nuclear materials, 2020-05, Vol.533 (1)

2020

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Investigating sluggish diffusion in a concentrated solid solution alloy using ion irradiation with in situ TEM

Intermetallics, 2019-07, Vol.110 (n/a), p.106461, Article 106461

2019

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Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys

Acta materialia, 2017-09, Vol.136 (C), p.390-401

2017

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Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy

Journal of nuclear materials, 2019-12, Vol.527 (C), p.151784, Article 151784

2019

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The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys

Journal of nuclear materials, 2020-05, Vol.533 (C), p.152105, Article 152105

2020

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Energetic particle irradiation study of TiN coatings: are these films appropriate for accident tolerant fuels?

Journal of nuclear materials, 2018-12, Vol.512 (C), p.239-245

2018

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Data on Cu- and Ni-Si-Mn-rich solute clustering in a neutron irradiated austenitic stainless steel

Data in brief, 2022-06, Vol.42 (n.a.), p.108263-108263, Article 108263

2022

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Corrigendum to “Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation”

Journal of nuclear materials, 2022-01, Vol.558, p.153197, Article 153197

2022

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Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

JPhys Energy, 2022-07, Vol.4 (3), p.34003

2022

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Characterisation of the spatial variability of material properties of Gilsocarbon and NBG-18 using random fields

Journal of nuclear materials, 2018-12, Vol.511 (C), p.91-108

2018

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Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration

Journal of nuclear materials, 2019-08, Vol.522 (C), p.111-122

2019

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Electron tomography of unirradiated and irradiated nuclear graphite

Journal of nuclear materials, 2021-03, Vol.545, p.152649, Article 152649

2021

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Data visualization heuristics for the physical sciences

Materials & design, 2019-10, Vol.179 (C), p.107868, Article 107868

2019

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Viewpoint: Nanoscale chemistry and crystallography are both the obstacle and pathway to advanced radiation-tolerant materials

Scripta materialia, 2018-01, Vol.143 (C), p.169-175

2018

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Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder

Acta materialia, 2019-03, Vol.166 (C), p.1-17

2019

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High temperature annealing of ion irradiated tungsten

Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys

The effect of electronic energy loss on irradiation-induced grain growth in nanocrystalline oxides

Influence of mechanical alloying and extrusion conditions on the microstructure and tensile properties of Low-Cr ODS FeCrAl alloys

Site specific, high-resolution characterisation of porosity in graphite using FIB-SEM tomography

Radiation induced amorphization of carbides in additively manufactured and conventional ferritic-martensitic steels: In-situ experiments on extraction replicas

Development of mesopores in superfine grain graphite neutron-irradiated at high fluence

Nanoprecipitates to Enhance Radiation Tolerance in High-Entropy Alloys

Microstructural investigation of an extruded austenitic oxide dispersion strengthened steel containing a carbon-containing process control agent

Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation

The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys

Investigating sluggish diffusion in a concentrated solid solution alloy using ion irradiation with in situ TEM

Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys

Influence of welding and neutron irradiation on dislocation loop formation and α′ precipitation in a FeCrAl alloy

The effect of Zr on precipitation in oxide dispersion strengthened FeCrAl alloys

Energetic particle irradiation study of TiN coatings: are these films appropriate for accident tolerant fuels?

Data on Cu- and Ni-Si-Mn-rich solute clustering in a neutron irradiated austenitic stainless steel

Corrigendum to “Deconvoluting the Effect of Chromium and Aluminum on the Radiation Response of Wrought FeCrAl Alloys After Low-Dose Neutron Irradiation”

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

Characterisation of the spatial variability of material properties of Gilsocarbon and NBG-18 using random fields

Microstructural evaluation of a Fe-12Cr nanostructured ferritic alloy designed for impurity sequestration

Electron tomography of unirradiated and irradiated nuclear graphite

Data visualization heuristics for the physical sciences

Viewpoint: Nanoscale chemistry and crystallography are both the obstacle and pathway to advanced radiation-tolerant materials

Multiscale investigations of nanoprecipitate nucleation, growth, and coarsening in annealed low-Cr oxide dispersion strengthened FeCrAl powder

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