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

Journal of nuclear materials, 2024-04, Vol.591 (C), p.154916, Article 154916

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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Oxidation of UN/U2N3-UO2 composites: an evaluation of UO(2 )as an oxidation barrier for the nitride phases

Journal of nuclear materials, 2021-02, Vol.544

2021

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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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An overview and recent progress in the heterogeneous photocatalytic reduction of U(VI)

Journal of photochemistry and photobiology. C, Photochemistry reviews, 2019-12, Vol.41, p.100320, Article 100320

2019

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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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Highly efficient uranium extraction by a piezo catalytic reduction-oxidation process

Applied catalysis. B, Environmental, 2022-08, Vol.310, p.121343, Article 121343

2022

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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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The effect of Ce–Zr on NH3-SCR activity over MnOx(0.6)/Ce0.5Zr0.5O2 at low temperature

Chemical engineering journal (Lausanne, Switzerland : 1996), 2014-01, Vol.236, p.171-180

2014

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Simulation of melted UO2 on a 90° bend channel by using the moving particle semi-implicit method for reactor core catcher development

Nuclear engineering and design, 2024-10, Vol.427, p.113413, Article 113413

2024

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An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment

Journal of nuclear materials, 2021-09, Vol.553, p.153053, Article 153053

2021

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In-situ high resolution photoelectron spectroscopy study on interaction of sodium with UO2+x film (0 ≤ x ≤ 1)

Journal of nuclear materials, 2021-03, Vol.545, p.152646, Article 152646

2021

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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

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

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

Oxidation of UN/U2N3-UO2 composites: an evaluation of UO(2 )as an oxidation barrier for the nitride phases

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

An overview and recent progress in the heterogeneous photocatalytic reduction of U(VI)

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

Highly efficient uranium extraction by a piezo catalytic reduction-oxidation process

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

The effect of Ce–Zr on NH3-SCR activity over MnOx(0.6)/Ce0.5Zr0.5O2 at low temperature

Simulation of melted UO2 on a 90° bend channel by using the moving particle semi-implicit method for reactor core catcher development

An evaluation of tri-valent oxide (Cr2O3) as a grain enlarging dopant for UO2 nuclear fuels fabricated under reducing environment

In-situ high resolution photoelectron spectroscopy study on interaction of sodium with UO2+x film (0 ≤ x ≤ 1)

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