Thermal treatment of neutron-irradiated nuclear graphite

tThe properties of graphite samples from the thermal column of a material testing reactor and from theinternals of two different nuclear power reactors were investigated regarding the thermal release oftritium and radiocarbon. These reactor types have been selected due to the different conditions underwhich graphite has been irradiated with neutrons during the operating time of these reactors. Based onthe findings, options for thermal treatment of irradiated graphite are discussed in order to facilitate itsfinal disposal