Fusion Chantilly

Overview of the PSFC blanket and fuel cycle modelling activities

Challenges Related to Tritium Transport in Fusion Reactors: From Component to System Level

Intro to tritium in fusion 22.016

SOFE 2025

SOFE tritium course

TFG 2025

Upgraded tritium release model for run 3

LIBRA presentation (Edinburgh U visit)

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.

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