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High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

Corrosion science, 2020-05, Vol.167, p.108537, Article 108537

2020

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AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding

Nuclear engineering and technology, 2018-03, Vol.50 (2), p.223-228

2018

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Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Materials, 2022-03, Vol.15 (6), p.2322

2022

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Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Journal of nuclear materials, 2019-04, Vol.517, p.268-285

2019

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Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C

Corrosion science, 2020-11, Vol.176 (108936), p.108936-21, Article 108936

2020

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Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature range

Journal of nuclear materials, 2021-10, Vol.554 (554), p.153069, Article 153069

2021

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Gestion coordonnée des barrages du bassin du Niger

E3S Web of Conferences, 2022, Vol.346, p.2002

2022

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Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature

Journal of nuclear materials, 2022-01, Vol.558, p.153332, Article 153332

2022

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Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction

Acta materialia, 2020-10, Vol.199, p.453-468

2020

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Studies of second phase particles in different zirconium alloys using extractive carbon replica and an electrolytic anodic dissolution procedure

Journal of nuclear materials, 2002-10, Vol.305 (2), p.224-231

2002

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Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe

Journal of nuclear materials, 2017-05, Vol.488, p.267-286

2017

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Lessons from the last 30 years for future water resource management in national and transboundary basins

Water international, 2024-05, Vol.49 (3-4), p.255-266

2024

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Hydrogen contribution to the thermal expansion of hydrided Zircaloy-4 cladding tubes

Journal of nuclear materials, 2013-09, Vol.440 (1-3), p.169-177

2013

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Microstructural influence on high temperature creep flow of Zr–1%NbO alloy in near- α, ( α + β), and β temperature ranges in a high vacuum environment

Journal of nuclear materials, 2011, Vol.408 (1), p.116-124

2011

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Simulation of the β→α(O) Phase Transformation due to Oxygen Diffusion during High Temperature Oxidation of Zirconium Alloys

Solid state phenomena, 2011, Vol.172-174, p.652-657

2011

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High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubes

Surface & coatings technology, 2018-09, Vol.349, p.1048-1057

2018

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Suivi hydrologique par altimétrie spatiale dans le bassin du Congo

Proceedings of the International Association of Hydrological Sciences, 2021, Vol.384, p.37-41

2021

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Oxygen, Hydrogen and Main Alloying Chemical Elements Partitioning Upon Alpha←→Beta Phase Transformation in Zirconium Alloys

Solid state phenomena, 2011, Vol.172-174, p.753-759

2011

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High-temperature mechanical properties improvement on modified 9Cr–1Mo martensitic steel through thermomechanical treatments

Journal of nuclear materials, 2010-10, Vol.405 (2), p.101-108

2010

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The French contribution to the management of transboundary hydrometerological networks

Houille blanche, 2014-02 (1), p.53-59

2014

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Tempering Kinetics of the X10CrMoVNb9-1Martensitic Steel

Solid state phenomena, 2011-06, Vol.172-174, p.845-850

2011

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Modelling of the Non-Isothermal Austenite Formation Kinetics of a X10CrMoVNb9-1 Martensitic Steel

Solid state phenomena, 2011-06, Vol.172-174, p.815-820

2011

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AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M6 cladding

Nuclear Engineering and Technology, 2018, 50(2), , pp.223-228

2018

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Creep flow and fracture behavior of the oxygen-enriched alpha phase in zirconium alloys

Scripta materialia, 2016-05, Vol.117, p.20-23

2016

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La contribution française en gestion de réseaux de mesures transfrontaliers

Houille blanche, 2014-02, Vol.100 (1), p.53-59

2014

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High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process

AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M5 cladding

Radiation-Induced Sharpening in Cr-Coated Zirconium Alloy

Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors

Breakaway oxidation of zirconium alloys exposed to steam around 1000 °C

Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature range

Gestion coordonnée des barrages du bassin du Niger

Mechanical behavior of a chromium coating on a zirconium alloy substrate at room temperature

Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction

Studies of second phase particles in different zirconium alloys using extractive carbon replica and an electrolytic anodic dissolution procedure

Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe

Lessons from the last 30 years for future water resource management in national and transboundary basins

Hydrogen contribution to the thermal expansion of hydrided Zircaloy-4 cladding tubes

Microstructural influence on high temperature creep flow of Zr–1%NbO alloy in near- α, ( α + β), and β temperature ranges in a high vacuum environment

Simulation of the β→α(O) Phase Transformation due to Oxygen Diffusion during High Temperature Oxidation of Zirconium Alloys

High-temperature oxidation resistance of chromium-based coatings deposited by DLI-MOCVD for enhanced protection of the inner surface of long tubes

Suivi hydrologique par altimétrie spatiale dans le bassin du Congo

Oxygen, Hydrogen and Main Alloying Chemical Elements Partitioning Upon Alpha←→Beta Phase Transformation in Zirconium Alloys

High-temperature mechanical properties improvement on modified 9Cr–1Mo martensitic steel through thermomechanical treatments

The French contribution to the management of transboundary hydrometerological networks

Tempering Kinetics of the X10CrMoVNb9-1Martensitic Steel

Modelling of the Non-Isothermal Austenite Formation Kinetics of a X10CrMoVNb9-1 Martensitic Steel

AREVA NP's enhanced accident-tolerant fuel developments: Focus on Cr-coated M6 cladding

Creep flow and fracture behavior of the oxygen-enriched alpha phase in zirconium alloys

La contribution française en gestion de réseaux de mesures transfrontaliers

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