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D. Gilbon

Microstructural evolution of ferritic-martensitic steels irradiated in the fast breeder reactor Phénix
1993 · P. Dubuisson, D. Gilbon, et al. · Journal of Nuclear Materials · 168
Hydrogen Content, Preoxidation, and Cooling Scenario Effects on Post-Quench Microstructure and Mechanical Properties of Zircaloy-4 and M5® Alloys in LOCA Conditions
2008 · J.-C. Brachet, V. Vandenberghe-Maillot, et al. · Journal of ASTM International · 91
Hydride embrittlement in ZIRCALOY-4 plate: Part II. interaction between the tensile stress and the hydride morphology
1994 · J. B. Bai, N. JI, et al. · Metallurgical and Materials Transactions A · 90
Irradiation Creep and Growth Behavior, and Microstructural Evolution of Advanced Zr-Base Alloys
2000 · D Gilbon, A Soniak, et al. · 74
Experimental study of the nucleation and growth of c-component loops under charged particle irradiations of recrystallized Zircaloy-4
2011 · L. Tournadre, F. Onimus, et al. · Journal of Nuclear Materials · 69
Influence of Iron in the Nucleation of ⟨c⟩ Component Dislocation Loops in Irradiated Zircaloy-4
1996 · Y de Carlan, C Regnard, et al. · 66
Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
2005 · S Doriot, D Gilbon, et al. · Journal of ASTM International · 62
Effect of Irradiation on the Microstructure of Zircaloy-4
1994 · D Gilbon, C Simonot · 60
HVEM study of the effects of alloying elements and impurities on radiation damage in Zr-alloys
1993 · Malcolm Griffiths, D. Gilbon, et al. · Journal of Nuclear Materials · 56
Toward a better understanding of the hydrogen impact on the radiation induced growth of zirconium alloys
2013 · L. Tournadre, F. Onimus, et al. · Journal of Nuclear Materials · 55
Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phénix Fuel Subassembly
1992 · JL Séran, V Lévy, et al. · 45
Microstructural Evolution of M5TM7 Alloy Irradiated in PWRs up to High Fluences—Comparison With Other Zr-Based Alloys
2014 · S. Doriot, B. Verhaeghe, et al. · 43
Effect of Alloying Elements, Cold Work, and Hydrogen on the Irradiation-Induced Growth Behavior of Zirconium Alloy Variants
2018 · Suresh Yagnik, Ronald Adamson, et al. · 42
Investigation of neutron radiation effects on the mechanical behavior of recrystallized zirconium alloys
2006 · F. Onimus, J.L. Béchade, et al. · Journal of Nuclear Materials · 42
In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4
2009 · Philippe Bossis, Bénédicte Verhaeghe, et al. · Journal of ASTM International · 38
Impact of an applied stress on c-component loops under Zr ion irradiation in recrystallized Zircaloy-4 and M5®
2015 · N. Gharbi, F. Onimus, et al. · Journal of Nuclear Materials · 32
Transmission electron microscopy study of second phase particles irradiated by 2 MeV protons at 350 °C in Zr alloys
2017 · S. Doriot, F. Onimus, et al. · Journal of Nuclear Materials · 29
Experimental Analysis of Slip Systems Activation in Neutron-Irradiated Zirconium Alloys and Comparison with Polycrystalline Model Simulations
2012 · F. Onimus, J. L. Béchade, et al. · Metallurgical and Materials Transactions A · 28
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Plastic Deformation of Irradiated Zirconium Alloys: TEM Investigations and Micro-Mechanical Modeling
2005 · F Onimus, J-L Béchade, et al. · Journal of ASTM International · 27
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The Effect of Phosphorus on the Radiation-Induced Microstructure of Stabilized Austenitic Stainless Steels
1992 · P Dubuisson, A Maillard, et al. · 25
New insights in structural characterization of zirconium alloys oxidation at high temperature
2012 · Dominique Gosset, Matthieu Le Saux, et al. · Journal of Nuclear Materials · 24
In PWR Comprehensive Study of High Burn-Up Corrosion and Growth Behavior of M5® and Recrystallized Low-Tin Zircaloy-4
2009 · Philippe Bossis, Bénédicte Verhaeghe, et al. · 22
Microstructural Stability of M5™ Alloy Irradiated up to High Neutron Fluences
2005 · S Doriot, D Gilbon, et al. · 22
Microstructural study by XRD profile analysis and tem obser vations on hydrided recrystallized zircaloy-4
1992 · J.B. Bai, N. Ji, et al. · Scripta Metallurgica et Materialia · 21
Influence of Steam Pressure on the High Temperature Oxidation and Post-Cooling Mechanical Properties of Zircaloy-4 and M5 Cladding (LOCA Conditions)
2014 · M. Le Saux, V. Vandenberghe, et al. · 17
Works count: 54
Citation count: 1,420
H-index: 22
I10-index: 32
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