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Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond

Journal of nuclear materials, 2024-10, Vol.599, p.155246, Article 155246

2024

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Thermal conductivity prediction of UO2-BeO composite fuels and related decisive features discovery via convolutional neural network

Acta materialia, 2022-11, Vol.240, p.118352, Article 118352

2022

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Modelling of UO2 thermal conductivity: Improvement of the irradiation defects contribution and uncertainty quantification

Nuclear engineering and design, 2023-06, Vol.407, p.112304, Article 112304

2023

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Modelling the thermal conductivity of (UxTh1−x)O2 and (UxPu1−x)O2

Journal of nuclear materials, 2015-11, Vol.466 (C), p.29-35

2015

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Thermal conductivity of UO2 pellets enhanced by a semi-continuous structure of Ti3SiC2

Ceramics international, 2023-07, Vol.49 (13), p.21737-21744

2023

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Realistic morphological models of weakly to strongly branched pore networks for the computation of effective properties

International journal of solids and structures, 2023-07, Vol.275, p.112249, Article 112249

2023

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Thermal conductivity and diffusion mechanisms of noble gases in uranium dioxide: A DFT+U study

Journal of nuclear materials, 2019-08, Vol.521, p.137-145

2019

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Thermal conductivity variation in uranium dioxide with gadolinia additions

Journal of nuclear materials, 2020-11, Vol.540, p.152258, Article 152258

2020

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Graphite flakes/UO2 fuel pellets with excellent thermal conductivity in radial direction

Journal of nuclear materials, 2021-03, Vol.545, p.152639, Article 152639

2021

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In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity

Ceramics international, 2021-11, Vol.47 (22), p.31160-31167

2021

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UO2–Mo–Be composites for Accident Tolerant Fuel: SPS fabrication, microcracks-free in as-fabricated state and superior thermal conductivity

Ceramics international, 2020-12, Vol.46 (18), p.28939-28948

2020

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Interface interactions in UN-X-UO2 systems (X = V, Nb, Ta, Cr, Mo, W) by pressure-assisted diffusion experiments at 1773 K

Journal of nuclear materials, 2022-04, Vol.561, p.153554, Article 153554

2022

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Finite element modeling of UN-UO 2 and UN-X-UO 2 (X=Mo, W) composite nuclear fuels: temperature-dependent thermal conductivity and fuel performance

Nuclear materials and energy, 2023

2023

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Thermal conductivity of UO2 and PuO2 from first-principles

Journal of alloys and compounds, 2015-04, Vol.628, p.267-271

2015

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Thermophysical properties of urania-zirconia (U,Zr)O2 mixed oxides by molecular dynamics

Journal of nuclear materials, 2020-01, Vol.528, p.151876, Article 151876

2020

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Development status of microcell UO2 pellet for accident-tolerant fuel

Nuclear engineering and technology, 2018-03, Vol.50 (2), p.253-258

2018

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Post-irradiation examinations of UO2 composites as part of the Accident Tolerant Fuels Campaign

Journal of nuclear materials, 2019-04, Vol.517 (C), p.97-105

2019

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Thermophysical properties of liquid UO2, ZrO2 and corium by molecular dynamics and predictive models

Journal of nuclear materials, 2017-08, Vol.491, p.126-137

2017

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Evaluation of thermomechanical behaviors of UO2-5 vol% Mo nuclear fuel pellets with sandwiched configuration

Journal of nuclear materials, 2020-10, Vol.539, p.152295, Article 152295

2020

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UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study

Nuclear engineering and design, 2022-11, Vol.398 (1), p.111972, Article 111972

Greenquist, Ian

2022

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Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives

Journal of nuclear materials, 2020-11, Vol.540, p.152334, Article 152334

2020

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Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation

Journal of nuclear materials, 2014-11, Vol.454 (1-3), p.283-289

2014

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Development of thermal conductivity model with use of a thermal resistance circuit for metallic UO2 microcell nuclear fuel pellets

Nuclear Engineering and Technology, 2023, 55(10), , pp.3860-3865

2023

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Thermophysical properties of U, Zr-oxides as prototypic corium materials

Journal of nuclear materials, 2019-07, Vol.520, p.165-177

2019

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Optimization of Conductive Fins to Minimize UO2 Fuel Temperature and Radial Temperature Gradient

Energies (Basel), 2023-03, Vol.16 (6), p.2785

2023

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Conductivity of UO2 ceramics: Effect of a weakly to strongly branched pore network up to 500 ∘C (exp) and numerical simulations beyond

Thermal conductivity prediction of UO2-BeO composite fuels and related decisive features discovery via convolutional neural network

Modelling of UO2 thermal conductivity: Improvement of the irradiation defects contribution and uncertainty quantification

Modelling the thermal conductivity of (UxTh1−x)O2 and (UxPu1−x)O2

Thermal conductivity of UO2 pellets enhanced by a semi-continuous structure of Ti3SiC2

Realistic morphological models of weakly to strongly branched pore networks for the computation of effective properties

Thermal conductivity and diffusion mechanisms of noble gases in uranium dioxide: A DFT+U study

Thermal conductivity variation in uranium dioxide with gadolinia additions

Graphite flakes/UO2 fuel pellets with excellent thermal conductivity in radial direction

In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity

UO2–Mo–Be composites for Accident Tolerant Fuel: SPS fabrication, microcracks-free in as-fabricated state and superior thermal conductivity

Interface interactions in UN-X-UO2 systems (X = V, Nb, Ta, Cr, Mo, W) by pressure-assisted diffusion experiments at 1773 K

Finite element modeling of UN-UO 2 and UN-X-UO 2 (X=Mo, W) composite nuclear fuels: temperature-dependent thermal conductivity and fuel performance

Thermal conductivity of UO2 and PuO2 from first-principles

Thermophysical properties of urania-zirconia (U,Zr)O2 mixed oxides by molecular dynamics

Development status of microcell UO2 pellet for accident-tolerant fuel

Post-irradiation examinations of UO2 composites as part of the Accident Tolerant Fuels Campaign

Thermophysical properties of liquid UO2, ZrO2 and corium by molecular dynamics and predictive models

Evaluation of thermomechanical behaviors of UO2-5 vol% Mo nuclear fuel pellets with sandwiched configuration

UO2-liquid metal suspension fuel concept for enhanced passive safety of LWRs: A heat pipe case study

Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives

Microstructure changes and thermal conductivity reduction in UO2 following 3.9 MeV He2+ ion irradiation

Development of thermal conductivity model with use of a thermal resistance circuit for metallic UO2 microcell nuclear fuel pellets

Thermophysical properties of U, Zr-oxides as prototypic corium materials

Optimization of Conductive Fins to Minimize UO2 Fuel Temperature and Radial Temperature Gradient

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