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Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation

Journal of nuclear materials, 2020-10, Vol.539, p.152296, Article 152296

2020

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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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Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA

Journal of nuclear materials, 2020-05, Vol.533 (C), p.152076, Article 152076

2020

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Nanoindentation testing of high burn-up fast reactor mixed oxide fuel

Journal of nuclear materials, 2022-06, Vol.564, p.153668, Article 153668

2022

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3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms

Nuclear Engineering and Technology, 2021, 53(9), , pp.2968-2976

2021

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Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX

Journal of nuclear materials, 2021-08, Vol.551, p.152922, Article 152922

2021

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Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements

Journal of nuclear materials, 2021-12, Vol.557 (C), p.153280, Article 153280

2021

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Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)

Journal of nuclear materials, 2020-04, Vol.531 (C), p.151964, Article 151964

2020

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Post-irradiation characterization of a high burnup mixed oxide fuel rod with minor actinides

Journal of nuclear materials, 2022-04, Vol.562, p.153545, Article 153545

2022

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Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel

Journal of nuclear materials, 2021-05, Vol.548 (C), p.152843, Article 152843

2021

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Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels

Journal of nuclear materials, 2016-11, Vol.480, p.138-149

2016

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Laser melting of nano-crystalline uranium dioxide

Progress in nuclear energy (New series), 2014-04, Vol.72, p.11-16

2014

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High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide

Materials research express, 2014-06, Vol.1 (2), p.25034

2014

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Length scale effects of micro- and meso‑scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

Journal of nuclear materials, 2025-01, Vol.604, p.155469, Article 155469

2025

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Post-irradiation examinations of UO 2 composites as part of the Accident Tolerant Fuels Campaign

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

2019

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Grain subdivision and structural modifications by high-energy heavy ions in UO2 with different initial grain size

Nuclear instruments & methods in physics research. Section B, Beam interactions with materials and atoms, 2022-03, Vol.515, p.48-60

2022

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Post irradiation examinations of FeCrAl cladding in PWR conditions

Journal of nuclear materials, 2025-01, Vol.603 (C), p.155402, Article 155402

2025

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Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing

Journal of nuclear materials, 2022-10, Vol.569 (C), p.153881, Article 153881

2022

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3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms

Nuclear engineering and technology, 2021, Vol.53 (9), p.2968-2976

2021

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A semi-empirical model for the formation and depletion of the high burnup structure in UO2

Journal of nuclear materials, 2017-04, Vol.487, p.23-29

2017

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Microhardness and Young's modulus of high burn-up UO2 fuel

Journal of nuclear materials, 2016-10, Vol.479, p.447-454

2016

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A semi-empirical model for the formation and depletion of the high burnup structure in UO^sub 2

Journal of nuclear materials, 2017-04, Vol.486, p.23

2017

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A semi-empirical model for the formation and depletion of the high burnup structure in UO 2

Journal of nuclear materials, 2017-01, Vol.487 (C)

2017

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High frequency acoustic microscopy for the determination of porosity and Young's modulus in high burnup uranium dioxide nuclear fuel

2015 4th International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2015, p.1-5

2015

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La Riabilitazione Neuropsicologica: Un'analisi Basata Sul Metodo Evidence-Based Medicine

2012 edition., 2011

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Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation

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

Post-irradiation examinations of annular mixed oxide fuels with average burnup 4 and 5% FIMA

Nanoindentation testing of high burn-up fast reactor mixed oxide fuel

3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms

Electron microscopy characterization of the fuel-cladding interaction in medium burnup annular fast reactor MOX

Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements

Electron microscopy characterization of fast reactor MOX Joint Oxyde-Gaine (JOG)

Post-irradiation characterization of a high burnup mixed oxide fuel rod with minor actinides

Three-dimensional reconstruction from experimental two-dimensional images: Application to irradiated metallic fuel

Critical assessment of the pore size distribution in the rim region of high burnup UO2 fuels

Laser melting of nano-crystalline uranium dioxide

High-temperature and melting behaviour of nanocrystalline refractory compounds: an experimental approach applied to thorium dioxide

Length scale effects of micro- and meso‑scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

Post-irradiation examinations of UO 2 composites as part of the Accident Tolerant Fuels Campaign

Grain subdivision and structural modifications by high-energy heavy ions in UO2 with different initial grain size

Post irradiation examinations of FeCrAl cladding in PWR conditions

Detailed characterization of a PWR fuel rod at high burnup in support of LOCA testing

3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms

A semi-empirical model for the formation and depletion of the high burnup structure in UO2

Microhardness and Young's modulus of high burn-up UO2 fuel

A semi-empirical model for the formation and depletion of the high burnup structure in UO^sub 2

A semi-empirical model for the formation and depletion of the high burnup structure in UO 2

High frequency acoustic microscopy for the determination of porosity and Young's modulus in high burnup uranium dioxide nuclear fuel

La Riabilitazione Neuropsicologica: Un'analisi Basata Sul Metodo Evidence-Based Medicine

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