Tritium Breeding and transport in Molten Salts under 14 MeV neutron Irradiation: Insights from the LIBRA Experiment

deck

FESTIM: status and developments after 5 years of hydrogen transport modelling

FESTIM @ IPP

Slides for the FESTIM workshop held at IPP in September 2024

Advancements in Tritium Breeding: towards achieving self-sufficiency in Fusion Power Plants through Liquid Immersion Blanket Concept (SOFT 2024)

FESTIM meeting August

FESTIM @ UKAEA

FESTIM meeting July

AMPMI 2024

FESTIM meeting June

FESTIM @ CFS

FESTIM meeting April

Advancing Tritium Self-Sufficiency in Fusion Power Plants (HWS talk)

FESTIM meeting March

LIBRA project presentation

FESTIM meeting Jan

LIBRA project: first tritium breeding results (TFG talk)

Tritium Transport in Breeding Blankets (PSFC seminar)

Modelling hydrogen in materials: component to reactor scale

Introduction: hydrogen in fusion

Python workshop (PSFC)

Permeation rig design presentation

H-transport materials library

H transport modelling with FESTIM

FESTIM workshop

Wall Forum Seminar Garching

Hydrogen transport in tokamaks

This is the presentation I gave at my PhD defense on the 17th of October 2022

He-H interactions

FESTIM 0.8