Expert Opinion on the Security of 300 MW(e) Thorium-High Temperature Reactor-Prototypes

Automatic translation: The safety concept of the helium-cooled, graphite-moderated pebble bed reactor, as it results from the safety report /1/, can be summarize as follows: a) Because of the properties of the fuel (coated particles) and the fuel assemblies (fuel-graphite spheres) takes place during normal operation there is always a small release of fission products into the coolant. b) The physico-chemical properties of the fuel elements and the dynamic properties of the reactor are such that extensive damage to the core, as a result of which all or a large part of the Radioactive fission products contained in fuel assemblies are released can be excluded, in particular melting of the core be able. An additional system to prevent core meltdown, such as the core emergency cooling systems that are customary in water-moderated power reactors is therefore not required.