OSSFE closing

deck

Advancements in Fusion Energy: tritium fuel cycle and FESTIM's role in hydrogen transport simulation (Dassault Systems Seminar)

BABY-1L-run-2

Tritium Fuel Cycle Seminar (UCSD)

The tritium fuel cycle presents one of the most critical challenges for achieving sustainable fusion power. Tritium, a key fuel for fusion reactions, is both scarce and radioactive, requiring efficient production, handling, and recycling to support the operation of future fusion power plants. This seminar will explore the scientific and engineering hurdles associated with the tritium fuel cycle, including production, transport, storage, and recovery, as well as the stringent safety and environmental considerations. We will highlight ongoing research at the Plasma Science and Fusion Center (PSFC) aimed at addressing these challenges, with a focus on the development of tritium breeding blankets. These blankets are designed to produce tritium in situ by leveraging neutron interactions with lithium-containing materials. Our work includes experimental investigations, such as the LIBRA project, and advanced modeling efforts using the open-source hydrogen transport code FESTIM. Key topics will include the optimisation of tritium production and recovery, the role of material selection, and the integration of tritium systems with fusion reactor designs. By advancing these technologies, we aim to pave the way toward achieving tritium self-sufficiency, a cornerstone of viable fusion energy systems.

LIBRA data management strategy

IAEA CRP talk

LIBRA

HPC fusion workshop (Nov 2024)

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