A new study by the International Atomic Energy Agency (IAEA), Deuterium–Tritium Toroidal Magnetic Confinement Facilities (IAEA-TECDOC-2116), looks at decommissioning and waste management with respect to fusion facilities. Experimental fusion facilities are integral to advancing fusion research and informing the design of future power-producing plants. As some of these facilities enter decommissioning, early experience is being gained in dismantling activated components and managing radioactive waste, including tritiated materials.

This emerging body of experience provides an important foundation for developing the technical methodologies and waste management strategies that will be required for future facilities, where higher neutron fluences and larger tritium inventories are expected. This new publication is intended for fusion researchers and engineers actively involved in radioactive waste management for fusion, as well as decommissioning experts with practical experience and regulatory authorities.

This reflects the high emission rate of energetic neutrons, which are emitted with energies of about 14 MeV, characteristic of D-T plasmas.

IAEA says the decommissioning of deuterium–tritium (D-T) magnetic confinement fusion facilities has several unique aspects arising from their complex design and mode of operation, with neutron activated components being of particular importance. This reflects the high emission rate of energetic neutrons, which are emitted with energies of about 14 MeV, characteristic of D-T plasmas.