H. Palancher

Commissariat à l'Énergie Atomique et aux Énergies Alternatives — France

Materials Science · Physical Sciences

19h-index1.3kcitations93works3.62yr avg
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Research Topics

Nuclear Materials and Properties(65), Nuclear reactor physics and engineering(40), Fusion materials and technologies(29), Radioactive element chemistry and processing(25), X-ray Diffraction in Crystallography(14)

Publications92 total

Swelling behavior of high density U3Si2 dispersion fuel
Journal of Nuclear Materials·2025· 2 cited
Defect study in Xe-irradiated UO2 by XRD, TEM and PAS
Journal of Nuclear Materials·2025· 1 citedOpen Access
Swelling Behavior of High Density U3si2 Dispersion Fuel
SSRN Electronic Journal·2025Open Access
Recent developments in coupled experiments and simulation to understand the fluid–structure dynamics of a Pressurized Water Reactor fuel assembly
Nuclear Engineering and Design·2024· 6 citedOpen Access
Versatility of dislocation motions in polycrystalline UO2 deformed at 1550 °C investigated by TEM
Scripta Materialia·2024· 9 citedOpen Access
Effect of Chromium Content on the On-Cooling Phase Transformations and Induced Prior-βZr Mechanical Hardening and Failure Mode (in Relation to Enhanced Accident-Tolerant Fuel Chromium-Coated Zirconium-Based Cladding Behavior upon and after High-Temperature Transients)
2023
Microstructural characterization of atomized U3Si2 powders with different silicon contents (7.4–7.8 wt%)
Journal of Nuclear Materials·2022· 3 citedOpen Access
Morphological and microstructural characterizations of the fresh fuel plates for the SEMPER FIDELIS in-pile test
Journal of Nuclear Materials·2022· 2 citedOpen Access
Assessing the impact of fabrication stages on the microstructural properties and the µ-hardness of as fabricated U-Mo dispersed fuel
HAL (Le Centre pour la Communication Scientifique Directe)·2021
Short communication: Spark plasma sintering as an innovative process for nuclear fuel plate manufacturing
Journal of Nuclear Materials·2020· 5 citedOpen Access
Microstructure evolution and phase transformation of heavy-ion irradiated U–Mo/Al fuels
Journal of Nuclear Materials·2020· 3 cited
From arc-melted ingot to MTR fuel plate: A SEM/EBSD microstructural study of U3Si2
Journal of Nuclear Materials·2020· 8 citedOpen Access
Evaluation of Equivalent Cladding Reacted parameters of Cr-coated claddings oxidized in steam at 1200 °C in relation with oxygen diffusion/partitioning and post-quench ductility
Journal of Nuclear Materials·2020· 72 citedOpen Access
Morphological characterization of the fresh ZrN coated UMo powders used in EMPIrE irradiation experiment: A practical approach
Journal of Nuclear Materials·2020· 11 cited
High temperature steam oxidation of chromium-coated zirconium-based alloys: Kinetics and process
Corrosion Science·2020· 354 citedOpen Access
In situ control of oxygen partial pressure in a buffered UO2 fuel: A manufacturing process
Journal of the European Ceramic Society·2019· 2 citedOpen Access
Morphological characterization of UMo/ZrN fresh powders for the EMPIrE irradiation experiment by a statistical approach
2019
Influence of exogenous xenon atoms on the evolution kinetics of extended defects in polycrystalline UO2 using in situ TEM
Journal of Nuclear Materials·2018· 22 cited
The H2020 european project fuel for research reactors LEU–forever: leu fuels for medium and high power research reactors in Europe
SPIRE - Sciences Po Institutional REpository·2018
Multi-scale characterization of UMo/ZrN coated particles used in Al dispersion fuel for research reactors
SPIRE - Sciences Po Institutional REpository·2018
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Frequent Co-authors

Anne Bonnin(12), X. Iltis(10), Rémi Tucoulou(9), C. Onofri(8), C. Sabathier(8), J. F. Bérar(8), O. Tougait(6), W. Petry(6), M. Legros(5), John P. Lynch(5), B. Stepnik(5), J. Allenou(5), V. Honkimäki(5), T. Zweifel(5), G. Carlot(4), A. Leenaers(4), Jean‐Sébastien Micha(4), B. Rebours(4), Étienne Castelier(4), H. Rouquette(4)