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Annabelle Le Coq

Associate Technical Staff Member

Contact

LECOQAG@ORNL.GOV

Publications

May 2023

Mechanical Properties of Additively Manufactured 316L Stainless Steel Before and After Neutron…

ORNL Report

April 2023

Simulation of a TRISO MiniFuel irradiation experiment with data-informed uncertainty quantification

Journal: Nuclear Engineering and Design

February 2023

A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes

Journal: Journal of Nuclear Materials

November 2022

Post-Irradiation Examination of Yttrium Hydride Specimens at Oak Ridge National Laboratory

Conference Paper

November 2022

Sensitivity Analysis of TRISO Fuel Configuration in a MiniFuel Irradiation Experiment

Conference Paper

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