Council Directive 2011/70/EuratomShow full title

Article 3 Definitions

For the purpose of this Directive the following definitions shall apply:

(1)

‘closure’ means the completion of all operations at some time after the emplacement of spent fuel or radioactive waste in a disposal facility, including the final engineering or other work required to bring the facility to a condition that will be safe in the long term;

(2)

‘competent regulatory authority’ means an authority or a system of authorities designated in a Member State in the field of regulation of the safety of spent fuel or radioactive waste management as referred to in Article 6;

(3)

‘disposal’ means the emplacement of spent fuel or radioactive waste in a facility without the intention of retrieval;

(4)

‘disposal facility’ means any facility or installation the primary purpose of which is radioactive waste disposal;

(5)

‘licence’ means any legal document granted under the jurisdiction of a Member State to carry out any activity related to the management of spent fuel or radioactive waste, or to confer responsibility for siting, design, construction, commissioning, operation, decommissioning or closure of a spent fuel management facility or of a radioactive waste management facility;

(6)

‘licence holder’ means a legal or natural person having overall responsibility for any activity or facility related to the management of spent fuel or radioactive waste as specified in a licence;

(7)

‘radioactive waste’ means radioactive material in gaseous, liquid or solid form for which no further use is foreseen or considered by the Member State or by a legal or natural person whose decision is accepted by the Member State, and which is regulated as radioactive waste by a competent regulatory authority under the legislative and regulatory framework of the Member State;

(8)

‘radioactive waste management’ means all activities that relate to handling, pretreatment, treatment, conditioning, storage, or disposal of radioactive waste, excluding off-site transportation;

(9)

‘radioactive waste management facility’ means any facility or installation the primary purpose of which is radioactive waste management;

(10)

‘reprocessing’ means a process or operation, the purpose of which is to extract fissile and fertile materials from spent fuel for further use;

(11)

‘spent fuel’ means nuclear fuel that has been irradiated in and permanently removed from a reactor core; spent fuel may either be considered as a usable resource that can be reprocessed or be destined for disposal if regarded as radioactive waste;

(12)

‘spent fuel management’ means all activities that relate to the handling, storage, reprocessing, or disposal of spent fuel, excluding off-site transportation;

(13)

‘spent fuel management facility’ means any facility or installation the primary purpose of which is spent fuel management;

(14)

‘storage’ means the holding of spent fuel or of radioactive waste in a facility with the intention of retrieval.