Microstructural Analysis of Zirconia at the Fuel-Cladding Interface in Medium and High Burnup Irradiated Fuel Rods

Autor: C. Schneider, L. Fayette, Isabelle Zacharie-Aubrun, Jérôme Favergeon, Sébastien Chevalier, J. Sercombe, T. Blay

Publikováno v: Oxidation of Metals. 96:295-306

During irradiation in a nuclear reactor, the UO2 fuel and the Zr cladding come into contact due to fuel thermal expansion and cladding creep. The inner surface of the Zr cladding in contact with the UO2 fuel therefore oxidizes. This paper analyzes th

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::ac882eb2d17e7f99ff22b94ee688ffc3
https://doi.org/10.1007/s11085-021-10045-8

Restructuring in high burn-up UO2 fuels: Experimental characterization by electron backscattered diffraction

Autor: Isabelle Zacharie-Aubrun, Rebecca Dowek, Jean Noirot, Thierry Blay, Martiane Cabié, Myriam Dumont

Publikováno v: Journal of Applied Physics
Journal of Applied Physics, 2022, 132 (19), pp.195903. ⟨10.1063/5.0104865⟩

This paper discusses the use of electron backscattered diffraction to characterize restructuring in a set of UO2 samples, irradiated in a pressurized water reactor at a burn-up between 35 and 73 GWd/tU, including standard UO2 samples and Cr-doped UO2

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::efbb3a8946fd90ad52ca3a40929f70ce
https://doi.org/10.1063/5.0104865

Determination of the pressure in micrometric bubbles in irradiated nuclear fuels

Autor: Thierry Blay, Philippe Bienvenu, J. Noirot, Myriam Dumont, Rébecca Dowek, K. Hanifi, Isabelle Zacharie-Aubrun, Céline Cagna, Martiane Cabié, I. Roure

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, Elsevier, 2021, 543, pp.152591. ⟨10.1016/j.jnucmat.2020.152591⟩
Journal of Nuclear Materials, 2021, 543, pp.152591. ⟨10.1016/j.jnucmat.2020.152591⟩

In oxide nuclear fuels, at high burn-up or during high temperature periods such as ramp tests, out-of- pile heating tests, or any irradiations at high linear heat rates, fission gases can form micrometric or quasi-micrometric bubbles. During nominal

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f55174b4445d799e35ecf93e84a8fbbf
https://hal.archives-ouvertes.fr/hal-03385660/file/MSMP_JNUCMAT_2021_DUMONT.pdf

MOX fuel microstructural evolution during the VERDON-3 and 4 tests

Autor: I. Roure, Isabelle Zacharie-Aubrun, K. Hanifi, L. Fayette, Philippe Bienvenu, I. Félines, Fabienne Audubert, Yves Pontillon, Jean-Louis Hazemann, S. Reboul, C. Le Gall, Thierry Blay

Publikováno v: Journal of Nuclear Materials
Journal of Nuclear Materials, 2020, 531, pp.152015. ⟨10.1016/j.jnucmat.2020.152015⟩

The VERDON-3 and -4 tests were part of the VERDON-ISTP programme that aimed at studying the fuel and fission products (FP) behaviour in severe accident conditions. The main objective of these two complementary tests was the study of MOX fuel behaviou

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::68de4cd8f6444f31f1595eb9fff3f123
https://hal.science/hal-04116996

UO2 micron scale specimen fracture: Parameter identification and influence of porosities

Autor: Sylvain Meille, Ronan Henry, Isabelle Zacharie-Aubrun, Jean-Marie Gatt, Aurélien Doitrand

Publikováno v: Theoretical and Applied Fracture Mechanics
Theoretical and Applied Fracture Mechanics, Elsevier, 2020, 108, pp.102665. ⟨10.1016/j.tafmec.2020.102665⟩
Theoretical and Applied Fracture Mechanics, 2020, 108, pp.102665. ⟨10.1016/j.tafmec.2020.102665⟩

International audience; Bending of micron-scale cantilevers with or without initial notch is simulated by finite element and their fracture is assessed using either the coupled criterion or a cohesive zone model. The fracture toughness and strength o

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5542fc254745308ab42d83b091d596c2
https://hal.archives-ouvertes.fr/hal-02780419/document