KEY DEADLINES
30 May 2025 Deadline for submission of abstracts through IAEA-INDICO for regular contributions. Deadline for participants to submit their application via the InTouch+ platform
11 July 2025 Notification of acceptance of abstracts and of assigned awards
Located at the very bottom of a magnetic fusion device in most designs, where impurities such as helium ‘ash’ are diverted, the divertor acts as the ‘exhaust pipe’ of the fusion machine and is where any excessive heat is channelled to. This configuration helps to produce ‘purer’ plasmas with better energy confinement — a critical parameter for the performance of a fusion device — ensuring the plasma is hot enough for long enough so that sustained fusion reactions can take place.
In ITER, the divertor will be made up of 54 ‘cassettes’, each weighing 10 tonnes. The conditions placed on the cassettes will be very demanding; facing steady heat fluxes of 10 to 20 megawatts per square metre, with parts exposed to temperatures of between 1000°C and 2000°C, the cassettes will need to be replaced by remote handling at least once during the machine’s lifetime. To deal with the extreme heat and damaging particles, the components facing the plasma will be armoured with tungsten, a material that has both low tritium absorption and the highest melting temperature of any natural element. Although ITER’s divertor design reflects the state of the art of our current understanding and capabilities from a physics and technology point of view, further developments will be required for future fusion power plants.
Objectives
The event aims to provide a forum for discussion and analysis of the latest findings and open issues related to divertors in fusion devices in the context of ITER, demonstration fusion power plants and next-step facilities. The participating authors are invited to put their abstract into this context and thereby provide contributions to this meeting that serve as a basis for discussions.
Target Audience
The event aims to bring together junior and senior scientific fusion project leaders, plasma physicists, including theoreticians and experimentalists, and experts (researchers and engineers) in the physics and technology of the divertor.
Guidance for Presentations
Presenters are recommended to contextualise their results in respect to broader applicability across different types and sizes of diverted magnetic confinement fusion devices. Emphasis should be given to highlighting relevance to reactor scale devices and reactor relevant operating scenarios. Scenarios such as long-pulse/steady-state operation, impact of transients/fluctuations, and the relevant timescales for the stability of a scenario (steady-state or time dependent).
Additionally, it would support the meeting if presenters could share identified gaps in the risks being addressed by the Divertor Concepts community. As well as lessons learned from the upgrades and modifications of devices. Modifications such as JET carbon to beryllium-tungsten wall change, DIII-D small angle slot divertor, and the new KSTAR tungsten divertor.
