Thank you to all participants of this meeting, for those of you who are also interested in Codes and Standards for Fusion, please see our Indico page for our November meeting: Technical Meeting on Experience in Codes and Standards for Fusion Technology (18-21 November 2025): Overview · Indico for IAEA Conferences

For their economical viability, fusion power plants based on a D-T fuel cycle will have to breed their own tritium in-situ. Yet, tritium breeding blankets are one of the most important and novel technical components in any planned next step devices to follow ITER. Many nations are embarking on dedicated R&D programmes to select tritum breeding blanket concepts which overcome issues, such as feasibility and attractiveness. 

Against this backdrop, the IAEA is launching a series of Technical Meetings on the topic of tritium breeding blankets and associated neutronics.

The objectives of the first Technical Meeting in the series are threefold: 

• Provide a forum for exchanging and discussing technical issues associated to the development and nuclear qualification of tritium breeding blanket technologies;

• Contribute to the establishment of specific guidelines for the qualification of tritium breeding blankets as part of fusion nuclear installations;

• Contribute to harvesting the return on experience from the ITER TBM Program to inform and support the development of breeding blankets for next step fusion facilities.