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A novel triphenylamine-based fluorescent probe for high selectivity and sensitivity detection of UO22+ in water samples and living cells

Dyes and pigments, 2025-01, Vol.232, p.112436, Article 112436

2025

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Diffusion in undoped and Cr-doped amorphous UO2

Journal of nuclear materials, 2023-04, Vol.576, p.154270, Article 154270

2023

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Phase relations and lattice parameter trends in Nd3+−substituted UO2 system under reducing and oxidizing conditions

Journal of nuclear materials, 2023-06, Vol.579, p.154396, Article 154396

2023

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The effect of cerium, neodymium, and ytterbium doping on UO2 dissolution

Journal of nuclear materials, 2024-01, Vol.591

2024

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UO2 solubility and chemical interactions in molten LiCl-Li2O

Journal of nuclear materials, 2024-10, Vol.599, p.155220, Article 155220

2024

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Modeling of fission gas diffusion and release for ▪ doped

Journal of nuclear materials, 2023-10, Vol.584, p.154575, Article 154575

2023

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Phase field simulation of pore morphological reconstruction and trailing bubbles in UO2 during pore migration

Nuclear engineering and design, 2024-08, Vol.425, p.113321, Article 113321

2024

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Fuel element microreactor integrating a square UO2 fuel rod with an internal heat pipe

Nuclear engineering and design, 2024-07, Vol.423, p.113205, Article 113205

2024

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Modelling radiation-induced oxidative dissolution of UO2-based spent nuclear fuel on the basis of the hydroxyl radical mediated surface mechanism

Journal of nuclear materials, 2023-05, Vol.578, p.154369, Article 154369

2023

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In-Situ TEM study of microstructural evolution in proton irradiated single crystal UO2 under high-temperature annealing

Acta materialia, 2024-12, Vol.281 (C), p.120440, Article 120440

2024

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Interaction between 1/2 {001} dislocations and {110} prismatic loops in uranium dioxide: Implications for strain-hardening under irradiation

International journal of plasticity, 2023-09, Vol.168, Article 103702

2023

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Insights into the UO2+x/U4O9 phase characterization in oxidized UO2 pellets as a function of hyper-stoichiometry

Frontiers in nuclear engineering, 2024-10, Vol.3

2024

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Hydrothermal synthesis of UO2 nanoparticles and their formation mechanism

Ceramics international, 2022-06, Vol.48 (11), p.16241-16250

2022

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Oxidation of UN/U2N3-UO2 composites: an evaluation of UO2 as an oxidation barrier for the nitride phases

Journal of nuclear materials, 2021-02, Vol.544, p.152700, Article 152700

2021

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Coated ZrN sphere-UO 2 composites as surrogates for UN-UO 2 accident tolerant fuels

Journal of nuclear materials, 2022, Vol.567, p.153845

2022

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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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Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2

Journal of nuclear materials, 2024-03, Vol.594

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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Z-Scheme heterojunction Cu2(OH)3F/Bi2WO6 with improved photocatalytic activity for uranium removal from wastewater under air atmosphere

Separation and purification technology, 2024-12, Vol.350, p.128012, Article 128012

2024

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Structural, compositional and morphological characterization of Nd3+-substituted UO2 microspheres obtained by ICHTJ sol–gel technique

Nuclear engineering and design, 2024-08, Vol.424, p.113308, Article 113308

2024

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Encapsulated additive nuclear fuels as an innovative accident tolerant fuel concept: fabrication, characterisation and oxidation resistance

Journal of nuclear materials, 2023

Costa, Diogo Ribeiro

2023

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Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating

Journal of nuclear materials, 2022-11, Vol.574 (-)

2022

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Role of microstructure on CO corrosion of SiC layer in UO₂-TRISO fuel

Journal of nuclear materials, 2020-04, Vol.537 (1)

2020

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Development of UO2 thermal diffusivity measurement with laser techniques

EPJ Web of conferences, 2021-01, Vol.253, p.07005

2021

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The effect of burnable absorbers on criticality and reactivity coefficient of VVER-1000 assembly

Nuclear technology & radiation protection, 2024, Vol.39 (1), p.12-20

2024

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A novel triphenylamine-based fluorescent probe for high selectivity and sensitivity detection of UO22+ in water samples and living cells

Diffusion in undoped and Cr-doped amorphous UO2

Phase relations and lattice parameter trends in Nd3+−substituted UO2 system under reducing and oxidizing conditions

The effect of cerium, neodymium, and ytterbium doping on UO2 dissolution

UO2 solubility and chemical interactions in molten LiCl-Li2O

Modeling of fission gas diffusion and release for ▪ doped

Phase field simulation of pore morphological reconstruction and trailing bubbles in UO2 during pore migration

Fuel element microreactor integrating a square UO2 fuel rod with an internal heat pipe

Modelling radiation-induced oxidative dissolution of UO2-based spent nuclear fuel on the basis of the hydroxyl radical mediated surface mechanism

In-Situ TEM study of microstructural evolution in proton irradiated single crystal UO2 under high-temperature annealing

Interaction between 1/2 {001} dislocations and {110} prismatic loops in uranium dioxide: Implications for strain-hardening under irradiation

Insights into the UO2+x/U4O9 phase characterization in oxidized UO2 pellets as a function of hyper-stoichiometry

Hydrothermal synthesis of UO2 nanoparticles and their formation mechanism

Oxidation of UN/U2N3-UO2 composites: an evaluation of UO2 as an oxidation barrier for the nitride phases

Coated ZrN sphere-UO 2 composites as surrogates for UN-UO 2 accident tolerant fuels

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

Performance and properties evolution of near-term accident tolerant fuel: Cr-doped UO2

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

Z-Scheme heterojunction Cu2(OH)3F/Bi2WO6 with improved photocatalytic activity for uranium removal from wastewater under air atmosphere

Structural, compositional and morphological characterization of Nd3+-substituted UO2 microspheres obtained by ICHTJ sol–gel technique

Encapsulated additive nuclear fuels as an innovative accident tolerant fuel concept: fabrication, characterisation and oxidation resistance

Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating

Role of microstructure on CO corrosion of SiC layer in UO₂-TRISO fuel

Development of UO2 thermal diffusivity measurement with laser techniques

The effect of burnable absorbers on criticality and reactivity coefficient of VVER-1000 assembly

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