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authFullName_s : J. Noirot
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Experimental Evidence of Oxygen Thermo-Migration in PWR UO$_2$ Fuels during Power Ramps using In-situ Oxido-Reduction Indicators

C. Riglet Martial , J. Sercombe , J. Lamontagne , J. Noirot , I. Roure , et al.
Journal of Nuclear Materials, 2016, 480, pp.32-39. ⟨10.1016/j.jnucmat.2016.07.056⟩
Journal articles cea-02389290v1
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MEXIICO a new equipment to study the pressure impact on the irradiated fuel behavior

E. Hanus , P. Malgouyres , S. Clement , R. Alloncle , M. Pontillon , et al.
Top Fuel Meeting 2016, Sep 2016, Boise, United States
Conference papers cea-02438357v1
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Effects of irradiation on mechanical properties of nuclear UO2 fuels evaluated by Vickers indentation at room temperature

I. Zacharie-Aubrun , R. Henry , Th. Blay , L. Brunaud , J. M. Gatt , et al.
Journal of Nuclear Materials, 2021, 547, ⟨10.1016/j.jnucmat.2021.152821⟩
Journal articles hal-03484852v1
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Size and radial origin of fragments formed while heating a 83 GWd/t$_U$ PWR fuel up to 1200 °C

J. Noirot , Th Blay , J. Lamontagne , L Fayette , Yves Pontillon , et al.
HRP / WGFS LOCA Workshop, May 2015, Aix-en-Provence, France
Conference papers cea-01599153v1
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fib/sem examination of a high burn-up uo2 in the center of the pellet

J. Noirot , I. Zacharie-Aubrun , T. Blay
WRFPM - 2017 Top Water Reactor Fuel Performance Meeting, Sep 2017, Jeju-do, South Korea
Conference papers hal-02418129v1

Nucleation and growth of intragranular defect and insoluble atom clusters in nuclear oxide fuels

P. Garcia , G. Martin , C. Sabathier , G. Carlot , A. Michel , et al.
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2011, 277, pp.98-108. ⟨10.1016/j.nimb.2011.12.031⟩
Journal articles istex in2p3-00658341v1
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A complementary approach to estimate the internal pressure of fission gas bubbles by SEM-SIMS-EPMA in irradiated nuclear fuels

C. Cagna , I. Zacharie-Aubrun , P. Bienvenu , L. Barrallier , B. Michel , et al.
IOP Conference Series: Materials Science and Engineering, 2016, 109, pp.012002. ⟨10.1088/1757-899X/109/1/012002⟩
Journal articles cea-02432835v1

Focused ion beam–scanning electron microscope examination of high burn-up UO 2 in the center of a pellet

J. Noirot , I. Zacharie-Aubrun , T. Blay
Nuclear Engineering and Technology, 2018, 50 (2), pp.259-267. ⟨10.1016/j.net.2017.12.002⟩
Journal articles cea-02428764v1

Hot cell laboratory needs in France

J. Noirot
ANS winter meeting, Oct 2017, Washington, United States
Conference papers hal-02416221v1

Electron probe microanalyses of transuranium elements in nuclear fuels and waste matrixes

M. Tribet , Xavier Deschanels , S. Peuget , C. Jegou , K. Hanifi , et al.
EMAS 2016, 12th Regional Workshop, May 2016, Bagnols-Sur-Ceze, France
Conference papers hal-02441956v1
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HIGH BURNUP CHANGES IN UO 2 FUELS IRRADIATED UP TO 83 GWd/t IN M5 ® CLADDINGS

J. Noirot , I Aubrun , L. Desgranges , K Hanifi , J. Lamontagne , et al.
Nuclear Engineering and Technology, 2009, 41 (2)
Journal articles hal-02010442v1

Detailed characterisations of High Burn-up Structures

J. Noirot , L. Desgranges , J. Lamontagne
Journal of Nuclear Materials, 2006, 372, ⟨10.1016/j.jnucmat.2007.04.037⟩
Journal articles istex cea-02355367v1

Analyse 3D par MEB-FIB de la porosite d'un combustible irradie

R. Dowek , J. Noirot , I. Zacharie-Aubrun , M. Dumont
Materiaux 2018, Nov 2018, Strasbourg, France
Conference papers hal-02411065v1

Some pending issues in nuclear fuel and in-core materials development for LWRs experimental support for modeling and simulation

J.-C. Brachet , C. Valot , Daniel Parrat , E. Federici , Yves Pontillon , et al.
OECD/NEA Workshop Enhancing experimental support for advancements in Nuclear fuels and materials, Jan 2018, Paris, France
Conference papers hal-02415308v1