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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, 2024-04, Vol.591, 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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Fuel element microreactor integrating a square UO2 fuel rod with an internal heat pipe

Nuclear engineering and design, 2024-07, Vol.423, 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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Impact of fission product (Ce, Sn, Sr, Se) oxides on UO2 oxidation to U3O8

Progress in nuclear energy (New series), 2024-06, Vol.171, Article 105194

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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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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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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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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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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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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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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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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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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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, 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, Article 113308

2024

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Stable and highly efficient extraction of U(VI) from seawater by covalent organic frameworks and amidoxime co-functionalized MXene

Colloids and surfaces. A, Physicochemical and engineering aspects, 2024-07, Vol.692, Article 133977

2024

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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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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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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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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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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

Modeling of fission gas diffusion and release for ▪ doped

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

Impact of fission product (Ce, Sn, Sr, Se) oxides on UO2 oxidation to U3O8

Hydrothermal synthesis of UO2 nanoparticles and their formation mechanism

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

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

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

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

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

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

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

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

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

Stable and highly efficient extraction of U(VI) from seawater by covalent organic frameworks and amidoxime co-functionalized MXene

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

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

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

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

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