Abstract
The properties of graphite samples from the thermal column of a material testing reactor and from the internals of two different nuclear power reactors were investigated regarding the thermal release of tritium and radiocarbon. These reactor types have been selected due to the different conditions under which graphite has been irradiated with neutrons during the operating time of these reactors. Based on the findings, options for thermal treatment of irradiated graphite are discussed in order to facilitate its final disposal.
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