AbstractCalculations have been made of the temperature evolution of the structures in the outboard zone and of the divertor of the standard and low-activation versions of the EEF (Environmental, Safety-Related, and Economic Potential of Fusion Power) Reference Reactor, following hypothesised loss-of-coolant events. For the standard version, temperatures of the first wall and blanket are found to rise only very slowly (after an initial adjustment) and for the low-activation version never exceed about 850 K. Although the results are specific to the particular materials and reactor power density used in this study, they augur well for the development of a purely passive approach to fusion safety.