Definitions
Article 2
For the purposes of this Regulation, the following definitions shall apply: 1. ‘non-nuclear-weapon Member States’ means Belgium, the Czech Republic, Denmark, Germany, Estonia, Greece, Spain, Ireland, Italy, Cyprus, Latvia, Lithuania, Luxembourg, Hungary, Malta, the Netherlands, Austria, Poland, Portugal, Slovenia, Slovakia, Finland and Sweden; 2. ‘nuclear-weapon Member States’ means France and the United Kingdom; 3. ‘third country’ means any State which is not a member of the European Atomic Energy Community; 4. ‘nuclear materials’ means ores, source materials or special fissile materials as defined in Article 197 of the Treaty; 5. ‘waste’ means nuclear material in concentrations or chemical forms considered as irrecoverable for practical or economic reasons and which may be disposed of; 6. ‘retained waste’ means waste, generated from processing or from an operational accident, measured or estimated on the basis of measurements, which has been transferred to a specific location within the material balance area from which it can be retrieved; 7. ‘conditioned waste’ means waste, measured or estimated on the basis of measurements, which has been conditioned in such a way (for example, in glass, cement, concrete or bitumen) that it is not suitable for further nuclear use; 8. ‘discards to the environment’ means waste, measured or estimated on the basis of measurements, which has been irrevocably discarded to the environment as the result of a planned discharge; 9. ‘categories’ (of nuclear material) are natural uranium, depleted uranium, uranium enriched in uranium-235 or uranium-233, thorium, plutonium, and any other material which the Council may determine, acting by a qualified majority on a proposal from the Commission; 10. ‘item’ means an identifiable unit such as a fuel assembly or a fuel pin; 11. ‘batch’ means a portion of nuclear material handled as a unit for accounting purposes at a key measurement point and for which the composition and quantity are defined by a single set of specifications or measurements. The nuclear material may be in bulk form or contained in a number of items; 12. ‘batch data’ means the total weight of each category of nuclear material and, in the case of plutonium and uranium, the isotopic composition when appropriate. For reporting purposes the weights of individual items in the batch shall be added together before rounding to the nearest unit; 13. ‘effective kilogram’ is a special unit used in safeguarding nuclear material, obtained by taking: (a) for plutonium, its weight in kilograms; (b) for uranium with an enrichment of 0,01 (1 %) and above, its weight in kilograms multiplied by the square of its enrichment; (c) for uranium with an enrichment below 0,01 (1 %) and above 0,005 (0,5 %), its weight in kilograms multiplied by 0,0001; and (d) for depleted uranium with an enrichment of 0,005 (0,5 %) or below, and for thorium, its weight in kilograms multiplied by 0,00005; 14. ‘material balance area’ means an area such that, for the purpose of establishing the material balance: (a) the quantity of nuclear material in each transfer into or out of each material balance area can be determined; and (b) the physical inventory of nuclear material in each material balance area can be determined when necessary in accordance with specified procedures; 15. ‘key measurement point’ means a location where nuclear material appears in such a form that it may be measured to determine material flow or inventory, including but not limited to, the places where nuclear material enters, leaves or is stored in, material balance areas; 16. ‘book inventory’ of a material balance area means the algebraic sum of the most recent physical inventory of that material balance area, and of all inventory changes that have occurred since that physical inventory was taken; 17. ‘physical inventory’ means the sum of all the measured batch quantities or derived estimates of batch quantities of nuclear material on hand at a given time within a material balance area, obtained in accordance with specified procedures; 18. ‘material unaccounted for’ means the difference between the physical inventory and the book inventory; 19. ‘shipper/receiver difference’ means the difference between the quantity of nuclear material in a batch as measured at the receiving material balance area and the quantity as stated by the shipping material balance area; 20. ‘source data’ means those data, recorded during measurement or calibration or used to derive empirical relationships, which identify nuclear material and provide batch data, including: weight of compounds; conversion factors to determine weight of element; specific gravity; element concentration; isotopic ratios; relationship between volume and manometer readings; and relationship between plutonium produced and power generated; 21. ‘site’ means an area delimited by the Community and the Member State, comprising one or more installations, including closed-down installations, as defined in their relevant basic technical characteristics, whereby: (a) waste treatment or waste storage installations do not constitute a site in themselves; (b) in the case of a closed-down installation where source material or special fissile material in quantities less than one effective kilogram was customarily used, the term is limited to locations with hot cells or where activities related to conversion, enrichment, fuel fabrication or reprocessing were carried out; (c) ‘site’ also includes all plants co-located with the installations which provide or use essential services including hot cells for processing irradiated materials not containing nuclear material; plants for the treatment, storage and disposal of waste; and buildings associated with activities specified in Annex 1 to Additional Protocol 1999/188/Euratom and identified by the State concerned; 22. ‘site representative’ means any person, undertaking or entity designated by the Member Stateas being responsible for the declarations referred to in Article 3(2); 23. ‘installation’ means a reactor, a critical installation, a conversion plant, a fabrication plant, a reprocessing plant, an isotope separation plant, a separate storage installation, a waste treatment or waste storage installation; or any other location where source material or special fissile material is customarily used; 24. ‘decommissioned installation’ means an installation for which it has been verified that residual structures and equipment essential for its use have been removed or rendered inoperable so that it is not used to store and can no longer be used to handle, process or utilise source material or special fissile material; 25. ‘closed-down installation’ means an installation for which it has been verified that operations have been stopped and the nuclear material removed but which has not been decommissioned.