L. Noirot

Oriented intra-granular bubble transport due to coupling of pinned bubble growth and dislocation climb

P. Maugis, L. Verma, L. Noirot, 2023, Journal of Nuclear Materials.

A method to calculate equilibrium concentrations of gas and defects in the vicinity of an over-pressured bubble in UO2

L. Noirot, 2014 .

3D simulation of a power ramp including fuel thermochemistry and oxygen thermodiffusion

P. Konarski, J. Sercombe, C. Riglet-Martial, 2019, Journal of Nuclear Materials.

Modeling high burnup fuel thermochemistry, fission product release and fuel melting during the VERDON 1 and RT6 tests

J. Sercombe, C. Riglet-Martial, C. Guéneau, 2022, Journal of Nuclear Materials.

Modelling intra-granular bubble movement and fission gas release during post-irradiation annealing of UO2 using a meso-scale and spatialized approach

P. Maugis, L. Verma, L. Noirot, 2020 .

A new spatially resolved model for defects and fission gas bubbles interaction at the mesoscale

P. Maugis, L. Verma, L. Noirot, 2019, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms.

MARGARET: A comprehensive code for the description of fission gas behavior

L. Noirot, L. Noirot, 2011 .

MARGARET: An Advanced Mechanistic Model of Fission Gas Behavior in Nuclear Fuel

Laurence Noirot, L. Noirot, 2006 .

Direct handling of sharp interfacial energy for microstructural evolution

V. Tikare, Luming Wang, E. Hernández-Rivera, 2014 .

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

P. Garcia, G. Carlot, C. Sabathier, 2012 .

Two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL

J. Sercombe, I. Ramière, B. Michel, 2021 .