Utfärdat i Wien i två exemplar den 22 september 1998 på danska, engelska, finska, franska, grekiska, italienska, nederländska, portugisiska, spanska, svenska och tyska språken, varvid varje språkversion skall äga lika giltighet, utom ifall de skulle skilja sig åt då de texter som ingåtts på IAEA:s styrelses officiella språk skall ha företräde.
\nPor el Gobierno del Reino de Bélgica For Kongeriget Belgiens regering Für die Regierung des Königreichs Belgien Για την κυβέρνηση τον Βασιλείου τον Βελγίου For the Government of the Kingdom of Belgium Pour le gouvernement du Royaume de Belgique Per il governo del Regno del Belgio Voor de regering van het Koninkrijk België Pelo Governo do Reino da Bélgica Belgian kuningaskunnan hallituksen puolesta För Konungariket Belgiens regering Mireille CLAEYS Por el Gobierno del Reino de Dinamarca For Kongeriget Danmarks regering Für die Regierung des Königreichs Dänemark Για την κυβέρνηση τον Βασιλείον του Δανίας For the Government of the Kingdom of Denmark Pour le gouvernement du Royaume de Danemark Per il governo del Regno di Danimarca Voor de regering van het Koninkrijk Denemarken Pelo Governo do Reino da Dinamarca Tanskan kuningaskunnan hallituksen puolesta För Konungariket Danmarks regering Henrik WØHLK Por el Gobierno de la República Federal de Alemania For Forbundsrepublikken Tysklands regering Für die Regierung der Bundesrepublik Deutschland Για την κυβέρνηση της Ομοσπονδιακής Δημοκρατίας της Γερμανίας For the Government of the Federal Republic of Germany Pour le gouvernement de la République fédérale d'Allemagne Per il governo della Repubblica federale di Germania Voor de regering van de Bondsrepubliek Duitsland Pelo Governo da República Federal da Alemanha Saksan liittotasavallan hallituksen puolesta För Förbundsrepubliken Tysklands regering Karl BORCHARD Helmut STAHL Por el Gobierno de la República Helénica For Den Hellenske Republiks regering Für die Regierung der Griechischen Republik Για την κυβέρνηση της Ελληνικής Δημοκρατίας For the Government of the Hellenic Republic Pour le gouvernement de la République hellénique Per il governo della Repubblica ellenica Voor de regering van de Helleense Republiek Pelo Governo da República Helénica Helleenien tasavallan hallituksen puolesta För Republiken Greklands regering Emmanuel FRAGOULIS Por el Gobierno del Reino de España For Kongeriget Spaniens regering Für die Regierung des Königreichs Spanien Για την κυβέρνηση του Βασιλείου της Ισπανίας For the Government of the Kingdom of Spain Pour le gouvernement du Royaume d'Espagne Per il governo del Regno di Spagna Voor de regering van het Koninkrijk Spanje Pelo Governo do Reino de Espanha Espanjan kuningaskunnan hallituksen puolesta För Konungariket Spaniens regering ad referendum Antonio Ortiz GARCÍA Por el Gobierno de Irlanda For Irlands regering Für die Regierung Irlands Για την κυβέρνηση της Ιρλανδίας For the Government of Ireland
\nPour le gouvernement de l'Irlande Per il governo dell'Irlanda Voor de regering van Ierland Pelo Governo da Irlanda Irlannin hallituksen puolesta För Irlands regering Thelma M. DORAN Por el Gobierno de la República Italiana For Den Italienske Republiks regering Für die Regierung der Italienischen Republik Για την κυβέρνηση της Ιταλικής Δημοκρατίας For the Government of the Italian Republic Pour le gouvernement de la République italienne Per il governo della Repubblica italiana Voor de regering van de Italiaanse Republiek Pelo Governo da República Italiana Italian tasavallan hallituksen puolesta För Republiken Italiens regering Vincenzo MANNO Por el Gobierno del Gran Ducado de Luxemburgo For Storhertugdømmet Luxembourgs regering Für die Regierung des Großherzogtums Luxemburg Για την κυβέρνηση του Μεγάλου Δουκάτου του Λουξεμβούργου For the Government of the Grand Duchy of Luxembourg Pour le gouvernement du Grand-Duché de Luxembourg Per il governo del Granducato di Lussemburgo Voor de regering van het Groothertogdom Luxemburg Pelo Governo do Grão-Ducado do Luxemburgo Luxemburgin suurherttuakunnan hallituksen puolesta För Storhertigdömet Luxemburgs regering Georges SANTER Por el Gobierno del Reino de los Países Bajos For Kongeriget Nederlandenes regering Für die Regierung des Königreichs der Niederlande Για την κυβέρνηση τον Βασιλείου των Κάτω Χωρών For the Government of the Kingdom of the Netherlands Pour le gouvernement du Royaume des Pays-Bas Per il governo del Regno dei Paesi Bassi Voor de regering van het Koninkrijk der Nederlanden Pelo Governo do Reino dos Países Baixos Alankomaiden kuningaskunnan hallituksen puolesta För Konungariket Nederländernas regering Hans A.F.M. FÖRSTER Por el Gobierno de la República de Austria For Republikken Østrigs regering Für die Regierung der Republik Österreich Για την κυβέρνηση της Δημοκρατίας της Αυστρίας For the Government of the Republic of Austria Pour le gouvernement de la République d'Autriche Per il governo della Repubblica d'Austria Voor de regering van de Republiek Oostenrijk Pelo Governo da República da Áustria Itävallan tasavallan hallituksen puolesta För Republiken Österrikes regering Irene FREUDENSCHUSS-REICHL Por el Gobierno de la República Portuguesa For Den Portugisiske Republiks regering Für die Regierung der Portugiesischen Republik Για την κυβέρνηση της Πορτογαλικής Δημοκρατίας For the Government of the Portuguese Republic Pour le gouvernement de la République portugaise Per il governo della Repubblica portoghese Voor de regering van de Portugese Republiek Pelo Governo da República Portuguesa
\nPortugalin tasavallan hallituksen puolesta För Republiken Portugals regering Álvaro José Costa DE MENDONÇA E MOURA Por el Gobierno de la República de Finlandia For Republikken Finlands regering Für die Regierung der Republik Finnland Για την κυβέρνηση της Φινλανδικής Δημοκρατίας For the Government of the Republic of Finland Pour le gouvernement de la République de Finlande Per il governo della Repubblica di Finlandia Voor de regering van de Republiek Finland Pelo Governo da República da Finlândia Suomen tasavallan hallituksen puolesta För Republiken Finlands regering Eva-Christina MÄKELÄINEN Por el Gobierno del Reino de Suecia For Kongeriget Sveriges regering Für die Regierung des Königreichs Schweden Για την κυβέρνηση τον Βασιλείου της Σονηδίας For the Government of the Kingdom of Sweden Pour le gouvernement du Royaume de Suède Per il governo del Regno di Svezia Voor de regering van het Koninkrijk Zweden Pelo Governo do Reino da Suécia Ruotsin kuningaskunnan hallituksen puolesta För Konungariket Sveriges regering Björn SKALA Por la Comunidad Europea de la Energía Atómica For Det Europæiske Atomenergifællesskab Für die Europäische Atomgemeinschaft Για την Ευρωπαϊκή Κοινότητα Ατομικής Ενέργειας For the European Atomic Energy Community Pour la Communauté européenne de l'énergie atomique Per la Comunità europea dell'energia atomica Voor de Europese Gemeenschap voor Atoomenergie Pela Comunidade Europeia da Energia Atómica Euroopan atomienergiayhteisön puolesta För Europeiska atomenergigemenskapen Lars-Erik LUNDIN Por el Organismo Internacional de Energía Atómica For Den Internationale Atomenergiorganisation Für die Internationale Atomenergie-Organisation Για τον Διεθνή Οργανισμό Ατομικής Ενέργειας For the International Atomic Energy Agency Pour l'Agence internationale de l'énergie atomique Per l'Agenzia internazionale dell'energia atomica Voor de Internationale Organisatie voor Atoomenergie Pela Agência Internacional da Energia Atómica Kansainvälisen atomienergiajärjestön puolesta För Internationella atomenergiorganet Mohamed ELBARADEI Annex IList of activities referred to in Article 2(a)(iv) of the Protocol(i) The manufacture of centrifuge rotor tubes or the assembly of gas centrifuges.Centrifuge rotor tubes means thin-walled cylinders as described at point 5.1.1(b) of Annex II.Gas centrifuges means centrifuges as described in the introductory note to point 5.1 of Annex II.(ii) The manufacture of diffusion barriers.Diffusion barriers means thin, porous filters as described in point 5.3.1(a) of Annex II.(iii) The manufacture or assembly of laser-based systems.Laser-based systems means systems incorporating those items as described in point 5.7 of Annex II.(iv) The manufacture or assembly of electromagnetic isotope separators.Electromagnetic isotope separators means those items referred to in point 5.9.1 of Annex II containing ion sources as described in 5.9.1(a) of Annex II.(v) The manufacture or assembly of columns or extraction equipment.Columns or extraction equipment means those items as described in points 5.6.1, 5.6.2, 5.6.3, 5.6.5, 5.6.6, 5.6.7 and 5.6.8 of Annex II.(vi) The manufacture of aerodynamic separation nozzles or vortex tubes.Aerodynamic separation nozzles or vortex tubes means separation nozzles and vortex tubes as described respectively in points 5.5.1 and 5.5.2 of Annex II.(vii) The manufacture or assembly of uranium plasma generation systems.Uranium plasma generation systems means systems for the generation of uranium plasma as described in point 5.8.3 of Annex II.(viii) The manufacture of zirconium tubes.Zirconium tubes means tubes as described in point 1.6 of Annex II.(ix) The manufacture or upgrading of heavy water or deuterium.Heavy water or deuterium means deuterium, heavy water (deuterium oxide) and any other deuterium compound in which the ratio of deuterium to hydrogen atoms exceeds 1:5 000.(x) The manufacture of nuclear grade graphite.Nuclear grade graphite means graphite having a purity level better than five parts per million boron equivalent and with a density greater than 1,50 g/cm3.(xi) The manufacture of flasks for irradiated fuel.A flask or irradiated fuel means a vessel for the transportation and/or storage of irradiated fuel which provides chemical, thermal and radiological protection, and dissipated decay heat during handling, transportation and storage.(xii) The manufacture of reactor control rods.Reactor control rods means rods as described in point 1.4 of Annex II.(xiii) The manufacture of criticality safe tanks and vessels.Criticality safe tanks and vessels means those items as described in points 3.2 and 3.4 of Annex II.(xiv) The manufacture of irradiated fuel element chopping machines.Irradiated fuel element chopping machines means equipment as described in point 3.1 of Annex II.(xv) The construction of hot cells.Hot cells means a cell or interconnected cells totalling at least 6 m3 in volume with shielding equal to or greater than the equivalent of 0,5 m of concrete, with a density of 3,2 g/cm3 or greater, outfitted with equipment for remote operations.Annex IIList of specified equipment and non-nuclear materialfor the reporting of exports and imports according to Article 2(a)(ix)1.
\nREACTORS AND EQUIPMENT THEREFOR1.1. Complete nuclear reactorsNuclear reactors capable of operation so as to maintain a controlled self-sustaining fission chain reaction, excluding zero energy reactors, the latter being defined as reactors with a designed maximum rate of production of plutonium not exceeding 100 grams per year. Explanatory noteA `nuclear reactor` basically includes the items within or attached directly to the reactor vessel, the equipment which controls the level of power in the core, and the components which normally contain or come in direct contact with or control the primary coolant of the reactor core.It is not intended to exclude reactors which could reasonably be capable of modification to produce significantly more than 100 grams of plutonium per year.
\nReactors designed for sustained operation at significant power levels, regardless of their capacity for plutonium production, are not considered as `zero energy reactors`.1.2. Reactor pressure vesselsMetal vessels, as complete units or as major shop-fabricated parts therefor, which are especially designed or prepared to contain the core of a nuclear reactor as defined in paragraph 1.1 and are capable of withstanding the operating pressure of the primary coolant.Explanatory noteA top plate for a reactor pressure vessel is covered by item 1.2 as a major shop-fabricated part of a pressure vessel.Reactor internals (e.g. support columns and plates for the core and other vessel internals, control rod guide tubes, thermal shields, baffles, core grid plates, diffuser plates, etc.) are normally supplied by the reactor supplier.
\nIn some cases, certain internal support components are included in the fabrication of the pressure vessel. These items are sufficiently critical to the safety and reliability of the operation of the reactor (and, therefore, to the guarantees and liability of the reactor supplier), so that their supply, outside the basic supply arrangement for the reactor itself, would not be common practice. Therefore, although the separate supply of these unique, especially designed and prepared, critical, large and expensive items would not necessarily be considered as falling outside the area of concern, such a mode of supply is considered unlikely.1.3. Reactor fuel charging and discharging machinesManipulative equipment especially designed or prepared for inserting or removing fuel in a nuclear reactor as defined in paragraph 1.1 capable of on-load operation or employing technically sophisticated positioning or alignment features to allow complex off-load fuelling operations such as those in which direct viewing of or access to the fuel is not normally available.1.4.
\nReactor control rodsRods especially designed or prepared for the control of the reaction rate in a nuclear reactor as defined in paragraph 1.1.Explanatory noteThis item includes, in addition to the neutron absorbing part, the support or suspension structures therefor is supplied separately.1.5. Reactor pressure tubesTubes which are especially designed or prepared to contain fuel elements and the primary coolant in a reactor as defined in paragraph 1.1 at an operating pressure in excess of 5,1 MPa (740 psi).1.6. Zirconium tubesZirconium metal and alloys in the form of tubes or assemblies of tubes, and in quantities exceeding 500 kg in any period of 12 months, especially designed or prepared for use in a reactor as defined in paragraph 1.1, and in which the relation of hafnium to zirconium is less than 1:500 parts by weight.1.7.
\nPrimary coolant pumpsPumps especially designed or prepared for circulating the primary coolant for nuclear reactors as defined in paragraph 1.1.Explanatory noteEspecially designed or prepared pumps may include elaborate sealed or multisealed systems to prevent leakage of primary coolant, canned-driven pumps, and pumps with inertial mass systems. This definition encompasses pumps certified to NC-1 or equivalent standards.2. NON-NUCLEAR MATERIALS FOR REACTORS2.1. Deuterium and heavy waterDeuterium, heavy water (deuterium oxide) and any other deuterium compound in which the ratio of deuterium to hydrogen atoms exceeds 1:5000 for use in a nuclear reactor as defined in paragraph 1.1 in quantities exceeding 200 kg of deuterium atoms for any one recipient country in any period of 12 months.2.2.
\nNuclear grade graphiteGraphite having a purity level better than 5 parts per million boron equivalent and with a density greater than 1,50 g/cm3 for use in a nuclear reactor as defined in paragraph 1.1 in quantities exceeding 3 x 104 kg (30 tonnes) for any one recipient country in any period of 12 months.NoteFor the purpose of reporting, the government will determine whether or not the exports of graphite meeting the above specifications are for nuclear reactor use.3. PLANTS FOR THE REPROCESSING OF IRRADIATED FUEL ELEMENTS, AND EQUIPMENT ESPECIALLY DESIGNED OR PREPARED THEREFORIntroductory noteReprocessing irradiated nuclear fuel separates plutonium and uranium from intensely radioactive fission products and other transuranic elements.
\nDifferent technical processes can accomplish this separation. However, over the years purex has become the most commonly used and accepted process. Purex involves the dissolution of irradiated nuclear fuel in nitric acid, followed by separation of the uranium, plutonium, and fission products by solvent extraction using a mixture of tributyl phosphate in an organic diluent.Purex facilities have process functions similar to each other, including: irradiated fuel element chopping, fuel dissolution, solvent extraction, and process liquor storage. There may also be equipment for thermal denitration of uranium nitrate, conversion of plutonium nitrate to oxide or metal, and treatment of fission product waste liquor to a form suitable for long term storage or disposal.
\nHowever, the specific type and configuration of the equipment performing these functions may differ between purex facilities for several reasons, including the type and quantity of irradiated nuclear fuel to be reprocessed and the intended disposition of the recovered materials, and the safety and maintenance philosophy incorporated into the design of the facility.A `plant for the reprocessing of irradiated fuel elements` included the equipment and components which normally come in direct contact with and directly control the irradiated fuel and the major nuclear material and fission product processing streams.These processes, including the complete systems for plutonium conversion and plutonium metal production, may be identified by the measures taken to avoid criticality (e.g. by geometry), radiation exposure (e.g. by shielding), and toxicity hazards (e.g. by containment).Items of equipment that are considered to fall within the meaning of the phrase `and equipment especially designed or prepared` for the reprocessing of irradiated fuel elements include:3.1.
\nIrradiated fuel element chopping machinesIntroductory noteThis equipment breaches the cladding of the fuel to expose the irradiated nuclear material to dissolution. Especially designed metal cutting shears are the most commonly employed, although advanced equipment, such as lasers, may be used.Remotely operated equipment especially designed or prepared for use in a reprocessing plant as identified above and intended to cut, chop or shear irradiated nuclear fuel assemblies, bundles or rods.3.2. DissolversIntroductory noteDissolvers normally receive the chopped-up spent fuel. In these critically safe vessels, the irradiated nuclear material is dissolved in nitric acid and the remaining hulls removed from the process stream.Critically safe tanks (e.g. small diameter, annular or slab tanks) especially designed or prepared for use in a reprocessing plant as identified above, intended for dissolution of irradiated nuclear fuel and which are capable of withstanding hot, highly corrosive liquid, and which can be remotely loaded and maintained.3.3.
\nSolvent extractors and solvent extraction equipmentIntroductory noteSolvent extractors both receive the solution of irradiated fuel from the dissolvers and the organic solution which separates the uranium, plutonium, and fission products. Solvent extraction equipment is normally designed to meet strict operating parameters, such as long operating lifetimes with no maintenance requirements or adaptability to easy replacement, simplicity of operation and control, and flexibility for variations in process conditions.Especially designed or prepared solvent extractors such as packed or pulse columns, mixer settlers or centrifugal contactors for use in a plant for the reprocessing of irradiated fuel.
\nSolvent extractors must be resistant to the corrosive effect of nitric acid. Solvent extractors are normally fabricated to extremely high standards (including special welding and inspection and quality assurance and quality control techniques) out of low carbon stainless steels, titanium, zirconium, or other high quality materials.3.4. Chemical holding or storage vesselsIntroductory noteThree main process liquor streams result from the solvent extraction step. Holding or storage vessels are used in the further processing of all three streams, as follows:(a) the pure uranium nitrate solution is concentrated by evaporation and passed to a denitration process where it is converted to uranium oxide.
\nThis oxide is reused in the nuclear fuel cycle;(b) the intensely radioactive fission products solution is normally concentrated by evaporation and stored as a liquor concentrate. This concentrate may be subsequently evaporated and converted to a form suitable for storage or disposal;(c) the pure plutonium nitrate solution is concentrated and stored pending its transfer to further process steps. In particular, holding or storage vessels for plutonium solutions are designed to avoid criticality problems resulting from changes in concentration and form of this stream.Especially designed or prepared holding or storage vessels for use in a plant for the reprocessing of irradiated fuel. The holding or storage vessels must be resistant to the corrosive effect of nitric acid.
\nThe holding or storage vessels are normally fabricated of materials such as low carbon stainless steels, titanium or zirconium, or other high quality materials. Holding or storage vessels may be designed for remote operation and maintenance and may have the following features for control of nuclear criticality:(1) walls or internal structures with a boron equivalent of at least 2 %, or(2) a maximum diameter of 175 mm (7'') for cylindrical vessels, or(3) a maximum width of 75 mm (3'') for either a slab or annular vessel.3.5. Plutonium nitrate to oxide conversion systemIntroductory noteIn most reprocessing facilities, this final process involves the conversion of the plutonium nitrate solution to plutonium dioxide.
\nThe main functions involved in this process are: process feed storage and adjustment, precipitation and solid/liquor separation, calcination, product handling, ventilation, waste management, and process control.Complete systems especially designed or prepared for the conversion of plutonium nitrate to plutonium oxide, in particular adapted so as to avoid criticality and radiation effects and to minimise toxicity hazards.3.6. Plutonium oxide to metal production systemIntroductory noteThis process, which could be related to a reprocessing facility, involves the fluorination of plutonium dioxide, normally with highly corrosive hydrogen fluoride, to produce plutonium fluoride which is subsequently reduced using high purity calcium metal to produce metallic plutonium and a calcium fluoride slag.
\nThe main functions involved in this process are: fluorination (e.g. involving equipment fabricated or lined with a precious metal), metal reduction (e.g. employing ceramic crucibles), slag recovery, product handling, ventilation, waste management and process control.Complete systems especially designed or prepared for the production of plutonium metal, in particular adapted so as to avoid criticality and radiation effects and to minimise toxicity hazards.4. PLANTS FOR THE FABRICATION OF FUEL ELEMENTSA `plant for the fabrication of fuel elements` includes the equipment:(a) which normally comes in direct contact with, or directly processes, or controls, the production flow of nuclear material, or(b) which seals the nuclear material within the cladding.5.
\nPLANTS FOR THE SEPARATION OF ISOTOPES OF URANIUM AND EQUIPMENT, OTHER THAN ANALYTICAL INSTRUMENTS, ESPECIALLY DESIGNED OR PREPARED THEREFORItems of equipment that are considered to fall within the meaning of the phrase `equipment, other than analytical instruments, especially designed or prepared` for the separation of isotopes of uranium include:5.1. Gas centrifuges and assemblies and components especially designed or prepared for use in gas centrifugesIntroductory noteThe gas centrifuge normally consists of a thin-walled cylinder(s) of between 75 mm (3'') and 400 mm (16'') diameter contained in a vacuum environment and spun at high peripheral speed of the order of 300 m/s or more with its central axis vertical.
\nIn order to achieve high speed the materials of construction for the rotating components have to be of a high strength to density ratio and the rotor assembly, and hence its individual components, have to be manufactured to very close tolerances in order to minimise the imbalance. In contrast to other centrifuges, the gas centrifuge for uranium enrichment is characterised by having within the rotor chamber a rotating disc-shaped baffle(s) and a stationary tube arrangement for feeding and extracting to UF6 gas and featuring at least three separate channels, of which two are connected to scoops extending from the rotor axis towards the periphery of the rotor chamber. Also contained within the vacuum environment are a number of critical items which do not rotate and which although they are especially designed are not difficult to fabricate nor are they fabricated out of unique materials.
\nA centrifuge facility however requires a large number of these components, so that quantities can provide an important indication of end use.5.1.1. Rotating components(a) Complete rotor assembliesThin-walled cylinders, or a number of interconnected thin-walled cylinders, manufactured from one or more of the high strength to density ratio materials described in the explanatory note to this section. If interconnected, the cylinders are joined together by flexible bellows or rings as described in Section 5.1.1.(c) following. The rotor is fitted with an internal baffle(s) and end caps, as described in Section 5.1.1.(d) and (e) following, if in final form. However the complete assembly may be delivered only partly assembled.(b) Rotor tubesEspecially designed or prepared thin-walled cylinders with thickness of 12 mm (0,5'') or less, a diameter of between 75 mm (3'') and 400 mm (16''), and manufactured from one or more of the high strength to density ratio materials described in the explanatory note to this section.(c) Rings or bellowsComponents especially designed or prepared to give localised support to the rotor tube or to join together a number of rotor tubes.
\nThe bellows is a short cylinder of wall thickness 3 mm (0,12'') or less, a diameter of between 75 mm (3'') and 400 m (16''), having a convolute, and manufactured from one of the high strength to density ratio materials described in the explanatory note to this section.(d) BafflesDisc-shaped components of between 75 mm (3'') and 400 m (16'') diameter especially designed or prepared to be mounted inside the centrifuge rotor tube, in order to isolate the take-off chamber from the main separation chamber and, in some cases, to assist the UF6 gas circulation within the main separation chamber of the rotor tube, and manufactured from one of the high strength to density ratio materials described in the explanatory note to this section.(e) Top caps/bottom capsDisc-shaped components of between 75 mm (3'') and 400 (16'') diameter especially designed or prepared to fit to the ends of the rotor tube, and so contain the UF6 within the rotor tube, and in some cases to support, retain or contain as an integrated part an element of the upper bearing (top cap) or to carry the rotating elements of the motor and lower bearing (bottom cap), and manufactured from one of the high strength to density ratio materials described in the explanatory note to this section.Explanatory noteThe materials used for centrifuge rotating components are:(a) maraging steel capable of an ultimate tensile strength of 2,05 x 109 N/m2 (300 000 psi) or more,(b) aluminium alloys capable of an ultimate tensile strength of 0,46 x 109 N/m2 (67 000 psi) or more,(c) filamentary materials suitable for use in composite structures and having a specific modulus of 12,3 x 106 m or greater and a specific ultimate tensile strength of 0,3 x 106 m or greater (`Specific Modulus` is the Young's Modulus in N/m2 divided by the specific weight in N/m3; `Specific Ultimate Tensile Strength` is the ultimate tensile strength in N/m2 divided by the specific weight in N/m3.5.1.2.
\nStatic components(a) Magnetic suspension bearingsEspecially designed or prepared bearing assemblies consisting of an annular magnet suspended within a housing containing a damping medium. The housing will be manufactured from a UF6-resistant material (see explanatory note to Section 5.2). The magnet couples with a pole piece or a second magnet fitted to the top cap described in Section 5.1.1.(e). The magnet may be ring-shaped with a relation between outer and inner diameter smaller or equal to 1,6:1. The magnet may be in a form having an initial permeability of 0,15 H/m (120 000 in CGS units) or more, or a remanence of 98,5 % or more, or an energy product of greater than 80 kJ/m3 (107 gauss-oersteds).
\nIn addition to the usual material properties, it is a prerequisite that the deviation of the magnetic axes from the geometrical axes is limited to very small tolerances (lower than 0,1 mm or 0,004 in) or that homogeneity of the material of the magnet is specially called for.(b) Bearings/dampersEspecially designed or prepared bearings comprising a pivot/cup assembly mounted on a damper. The pivot is normally a hardened steel shaft with a hemisphere at one end with a means of attachment to the bottom cap described in section 5.1.1.(e) at the other. The shaft may however have a hydrodynamic bearing attached. The cup is pellet-shaped with a hemispherical indentation in one surface. These components are often supplied separately to the damper.(c) Molecular pumpsEspecially designed or prepared cylinders having internally machined or extruded helical grooves and internally machines bores.
\nTypical dimensions are as follows: 75 mm (3'') to 400 mm (16'') internal diameter, 10 mm (0,4'') or more wall thickness, with the length equal to or greater than the diameter. The grooves are typically rectangular in cross-section and 2 mm (0,08'') or more in depth.(d) Motor statorsEspecially designed or prepared ring-shaped stators for high speed multiphase AC hysteresis (or reluctance) motors for synchronous operation within a vacuum in the frequency range of 600-2 000 Hz and a power range of 50-1 000 VA. The stators consist of multiphase windings on a laminated low loss iron core comprised of thin layers typically 2,0 mm (0,08'') thick or less.(e) Centrifuge housing/recipientsComponents especially designed designed or prepared to contain the rotor tube assembly of a gas centrifuge.
\nThe housing consists of a rigid cylinder of wall thickness up to 30 mm (1,2'') with precision machined ends to locate the bearings and with one or more flanges for mounting. The machined ends are parallel to each other and perpendicular to the cylinder's longitudinal axis to within 0,05° or less. The housing may also be a honeycomb type structure to accommodate several rotor tubes. The housings are made of or protected by materials resistant to corrosion by UF6.(f) ScoopsEspecially designed or prepared tubes up to 12 mm (0,5'') internal diameter for the extraction of UF6 gas from within the rotor tube by a pilot tube action (that is, with an aperture facing into the circumferential gas flow within the rotor tube, for example by bending the end of a radially disposed tube) and capable of being fixed to the central gas extraction system.
\nThe tubes are made of or protected by materials resistant to corrosion by UF6.5.2. Especially designed or prepared auxiliary systems, equipment and components for gas centrifuge enrichment plantsIntroductory noteThe auxiliary systems, equipment and components for a gas centrifuge enrichment plant are the systems of plant needed to feed UF6 to the centrifuges, to link the individual centrifuges to each other to form cascades (or stages) to allow for progressively higher enrichments and to extract the `product` and `tails` UF6 from the centrifuges, together with the equipment required to drive the centrifuges or to control the plant.Normally UF6 is evaporated from the solid using heated autoclaves and is distributed in gaseous form to the centrifuges by way of cascade header pipework.
\nThe `product` and `tails` UF6 gaseous streams flowing from the centrifuges are also passed by way of cascade header pipework to cold traps (operating at about 203 K(-70 °C)) where they are condensed prior to onward transfer into suitable containers for transportation or storage. Because an enrichment plant consists of many thousands of centrifuges arranged in cascades there are many kilometres of cascade header pipework, incorporating thousands of welds with a substantial amount of repetition of layout. The equipment, components and piping systems are fabricated to very high vacuum and cleanliness standards.5.2.1. Feed systems/product and tails withdrawal systemsEspecially designed or prepared process systems including:- feed autoclaves (or stations), used for passing UF6 to the centrifuge cascades at up to 100 kPa (15 psi) and at a rate of 1 kg/h or more,- desublimers (or cold traps) used to remove UF6 from the cascades at up to 3 kPa (0,5 psi) pressure.
\nThe desublimers are capable of being chilled to 203 K (-70 °C) and heated to 343 K (70 °C),- `product` and `tails` stations used for trapping UF6 into containers.This plant, equipment and pipework is wholly made of or lined with UF6-resistant materials (see explanatory note to this section) and is fabricated to very high vacuum and cleanliness standards.5.2.2. Machine header piping systemsEspecially designed or prepared piping systems and header systems for handling UF6 within the centrifuge cascades. The piping network is normally of the `triple` header system with each centrifuge connected to each of the headers. There is thus a substantial amount of repetition in its form. It is wholly made of UF6-resistant materials (see explanatory note to this section) and is fabricated to very high vacuum and cleanliness standards.5.2.3.
\nUF6 mass spectrometers/ion sourcesEspecially designed or prepared magnetic or quadrupole mass spectrometers capable of taking `on-line` samples of feed, product or tails, from UF6 gas streams and having all of the following characteristics:1. unit resolution for atomic mass unit greater than 320;2. ion sources constructed of or lined with nichrome or monel or nickel plated;3. electron bombardment ionisation sources;4. having a collector system suitable for isotopic analysis.5.2.4. Frequency changersFrequency changers (also known as converters or invertors) especially designed or prepared to supply motor stators as defined under 5.1.2(d), or parts, components and subassemblies of such frequency changers having all of the following characteristics:1. a multiphase output of 600 to 2 000 Hz;2. high stability (with frequency control better than 0,1 %);3. low harmonic distortion (less than 2 %), and4. an efficiency of greater than 80 %.Explanatory noteThe items listed above either come into direct contact with the UF6 process gas or directly control the centrifuges and the passage of the gas from centrifuge to centrifuge and cascade to cascade.Materials resistant to corrosion by UF6 include stainless steel, aluminium, aluminium alloys, nickel or alloys containing 60 % or more nickel.5.3.
\nEspecially designed or prepared assemblies and components for use in gaseous diffusion enrichmentIntroductory noteIn the gaseous diffusion method of uranium isotope separation, the main technological assembly is a special porous gaseous diffusion barrier, heat exchanger for cooling the gas (which is heated by the process of compression), seal valves and control valves, and pipelines. Inasmuch as gaseous diffusion technology uses uranium hexafluoride (UF6), all equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must be made of materials that remain stable in contact with UF6. A gaseous diffusion facility requires a number of these assemblies, so that quantities can provide an important indication of end use.5.3.1.
\nGaseous diffusion barriers(a) Especially designed or prepared thin, porous filters, with a pore size of 100-1 000 Å (angstroms), a thickness of 5 mm (0,2'') or less, and for tubular forms, a diameter of 25 mm (1'') or less, made of metallic, polymer or ceramic materials resistant to corrosion by UF6, and(b) especially prepared compounds or powders for the manufacture of such filters. Such compounds and powders include nickel or alloys containing 60 % or more nickel, aluminium oxide, or UF6-resistant fully fluorinated hydrocarbon polymers having a purity of 99,9 % or more, a particle size less than 10 microns, and a high degree of particle size uniformity, which are especially prepared for the manufacture of gaseous diffusion barriers.5.3.2.
\nDiffuser housingsEspecially designed or prepared hermetically sealed cylindrical vessels greater than 300 mm (12'') in diameter and greater than 900 mm (35'') in length, or rectangular vessels of comparable dimensions, which have an inlet connection and two outlet connections all of which are greater than 50 mm (2'') in diameter, for containing the gaseous diffusion barrier, made of or lined with UF6-resistant materials and designed for horizontal or vertical installation.5.3.3. Compressors and gas blowersEspecially designed or prepared axial, centrifugal, or positive displacement compressors, or gas blowers with a suction volume capacity of 1 m3/min. or more of UF6 and with a discharge pressure of up to several hundred kPa (100 psi), designed for long-term operation in the UF6 environment with or without an electrical motor of appropriate power, as well as separate assemblies of such compressors and gas blowers.
\nThese compressors and gas blowers have a pressure ratio between 2:1 and 6:1 and are made of, or lined with, materials resistant to UF6.5.3.4. Rotary shaft sealsEspecially designed or prepared vacuum seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor or the gas blower rotor with the driver motor so as to ensure a reliable seal against in-leaking of air into the inner chamber of the compressor or gas blower which is filled with UF6. Such seals are normally designed for a buffer gas in-leakage rate of less than 1 000 cm3/min (60 in3/min).5.3.5. Heat exchangers for cooling UF6Especially designed or prepared heat exchangers made of or lined with UF6-resistant materials (except stainless steel) or with copper or any combination of those metals, and intended for a leakage pressure change rate of less than 10 Pa (0,0015 psi) per hour under a pressure difference of 100 kPa (15 psi).5.4.
\nEspecially designed or prepared auxiliary systems, equipment and components for use in gaseous diffusion enrichmentIntroductory noteThe auxiliary systems, equipment and components for gaseous diffusion enrichment plants are the systems of plant needed to feed UF6 to the gaseous diffusion assembly, to link the individual assemblies to each other to form cascades (or stages) to allow for progressively higher enrichments and to extract the `product` and `tails` UF6 from the diffusion cascades. Because of the high inertial properties of diffusion cascades, any interruption in their operation, and especially their shutdown, leads to serious consequences. Therefore, a strict and constant maintenance of vacuum in all technological systems, automatic protection from accidents, and precise automated regulation of the gas flow is of importance in a gaseous diffusion plant.
\nAll this leads to a need to equip the plant with a large number of special measuring, regulating and controlling systems.Normally UF6 is evaporated from cylinders placed within autoclaves and is distributed in gaseous form to the entry point by way of cascade header pipework. The `product` and `tails` UF6 gaseous streams flowing from exit points are passed by way of cascade header pipework to either cold traps or to compression stations where the UF6 gas is liquefied prior to onward transfer into suitable containers for transportation or storage. Because a gaseous diffusion enrichment plant consists of a large number of gaseous diffusion assemblies arranged in cascades, there are many kilometres of cascade header pipework, incorporating thousands of welds with substantial amounts of repetition of layout.
\nThe equipment, components and piping systems are fabricated to very high vacuum and cleanliness standards.5.4.1. Feed systems/product and tails withdrawal systemsEspecially designed or prepared process systems, capable of operating at pressures of 300 kPa (45 psi) or less, including:- feed autoclaves (or systems), used for passing UF6 to the gaseous diffusion cascades,- desublimers (or cold traps) used to remove UF6 from diffusion cascades,- liquefaction stations where UF6 gas from the cascade is compressed and cooled to form liquid UF6,- `product` or `tails` stations used for transferring UF6 into containers.5.4.2. Header piping systemsEspecially designed or prepared piping systems and header systems for handling UF6 within the gaseous diffusion cascades.
\nThis piping network is normally of the `double` header system with each cell connected to each of the headers.5.4.3. Vacuum systems(a) Especially designed or prepared large vacuum manifolds, vacuum headers and vacuum pumps having a suction capacity of 5 m3/min. (175 ft3/min.) or more.(b) Vacuum pumps especially designed for service in UF6-bearing atmospheres made of, or lined with, aluminium, nickel, or alloys bearing more than 60 % nickel. These pumps may be either rotary or positive, may have displacement and fluorocarbon seals, and may have special working fluids present.5.4.4. Special shut-off and control valvesEspecially designed or prepared manual or automated shut-off and control bellows valves made of UF6-resistant materials with a diameter of 40 to 1 500 mm (1,5 to 59'') for installation in main and auxiliary systems of gaseous diffusion enrichment plants.5.4.5.
\nUF6 mass spectrometers/ion sourcesEspecially designed or prepared magnetic or quadrupole mass spectrometers capable of taking on-line samples of feed, product or tails, from UF6 gas streams and having all of the following characteristics:1. unit resolution for atomic mass unit greater than 320;2. ion sources constructed of or lined with nichrome or monel or nickel plated;3. Electron bombardment ionisation sources;4. collector system suitable for isotopic analysis.Explanatory noteThe items listed above either come into direct contact with the UF6 process gas or directly control the flow within the cascade. All surfaces which come into contact with the process gas are wholly made of, or lined with, UF6-resistant materials.
\nFor the purposes of the sections relating to gaseous diffusion items the materials resistant to corrosion by UF6 include stainless steel, aluminium, aluminium alloys, aluminium oxide, nickel or alloys containing 60 % or more nickel and UF6-resistant fully fluorinated hydrocarbon polymers.5.5. Especially designed or prepared systems, equipment and components for use in aerodynamic enrichment plantsIntroductory noteIn aerodynamic enrichment processes, a mixture of gaseous UF6 and light gas (hydrogen of helium) is compressed and then passed through separating elements wherein isotopic separation is accomplished by the generation of high centrifugal forces over a curved-wall geometry. Two processes of this type have been successfully developed: the separation nozzle process and the vortex tube process.
\nFor both processes the main components of a separation stage include cylindrical vessels housing the special separation elements (nozzles or vortex tubes), gas compressors and heat exchangers to remove the heat of compression. An aerodynamic plant requires a number of these stages, so that quantities can provide an important indication of end use. Since aerodynamic processes use UF6 all equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must be made of materials that remain stable in contact with UF6.Explanatory noteThe items listed in this section either come into direct contact with the UF6 process gas or directly control the flow within the cascade. All surfaces which come into contact with the process gas are wholly made of or protected by UF6-resistant materials.
\nFor the purpose of the section relating to aerodynamic enrichments items, the materials resistant to corrosion by UF6 include copper, stainless steel, aluminium, aluminium alloys, nickel or alloys containing 60 % or more nickel and UF6-resistant fully fluorinated hydrocarbon polymers.5.5.1. Separation nozzlesEspecially designed or prepared separation nozzles and assemblies thereof. The separation nozzles consist of slit-shaped, curved channels having a radius of curvature less than 1 mm (typically 0,1 to 0,05 mm), resistant to corrosion by UF6 and having a knife-edge within the nozzle that separates the gas flowing through the nozzle into two fractions.5.5.2. Vortex tubesEspecially designed or prepared vortex tubes and assemblies thereof.
\nThe vortex tubes are cylindrical or tapered, made of or protected by materials resistant to corrosion by UF6, having a diameter of between 0,5 cm and 4 cm, a length to diameter ratio of 20:1 or less and with one or more tangential inlets. The tubes may be equipped with nozzle-type appendages at either or both ends.Explanatory noteThe feed gas enters the vortex tube tangentially at one end or through swirl vanes or at numerous tangential positions along the periphery of the tube.5.5.3. Compressors and gas blowersEspecially designed or prepared axial, centrifugal or positive displacement compressors or gas blowers made of or protected by materials resistant to corrosion by UF6 and with a suction volume capacity of 2 m3/min. or more of UF6/carrier gas (hydrogen or helium) mixture.Explanatory noteThese compressors and gas blowers typically have a pressure ratio between 1.2:1 and 6:1.5.5.4.
\nRotary shaft sealsEspecially designed or prepared rotary shaft seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor rotor or the gas blower rotor with the driver motor so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or seal gas into the inner chamber of the compressor or gas blower which is filled with a UF6/carrier gas mixture.5.5.5. Heat exchangers for gas coolingEspecially designed or prepared heat exchangers made of or protected by materials resistant to corrosion by UF6.5.5.6. Separation element housingsEspecially designed or prepared separation element housings, made of or protected by materials resistant to corrosion by UF6, for containing vortex tubes or separation nozzles.Explanatory noteThese housings may be cylindrical vessels greater than 300 mm in diameter and greater than 900 mm in length, or may be rectangular vessels of comparable dimensions, and may be designed for horizontal or vertical installation.5.5.7.
\nFeed systems/product and tails withdrawal systemsEspecially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including:(a) feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process;(b) desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating;(c) solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form;(d) `product` or `tails` stations used for transferring UF6 into containers.5.5.8. Header piping systemsEspecially designed or prepared header piping systems, made of or protected by materials resistant to corrosion by UF6 for handling UF6 within the aerodynamic cascades.
\nThis piping network is normally of the `double` header design with each stage or group of stages connected to each of the headers.5.5.9. Vacuum systems and pumps(a) Especially designed or prepared vacuum systems having a suction capacity of 5 m3/min or more, consisting of vacuum manifolds, vacuum headers and vacuum pumps, and designed for service in UF6-bearing atmospheres.(b) Vacuum pumps especially designed or prepared for service in UF6-bearing atmospheres and made of or protected by materials resistant to corrosion by UF6. These pumps may use fluorocarbon seals and special working fluids.5.5.10. Special shut-off and control valvesEspecially designed or prepared manual or automated shut-off and control bellows valves made of or protected by materials resistant to corrosion by UF6 with a diameter of 40 to 1 500 mm for installation in main and auxiliary systems of aerodynamic enrichment plants.5.5.11.
\nUF6 mass spectrometers/ion sourcesEspecially designed or prepared magnetic or quadrupole mass spectrometers capable of taking `on-line` samples of feed, `product` or `tails`, from UF6 gas streams and having all of the following characteristics:1. unit resolution for mass greater than 320;2. ion sources constructed of or lined with nichrome or monel or nickel plated;3. electron bombardment ionisation sources;4. collector system suitable for isotopic analysis.5.5.12. UF6/carrier gas separation systemsEspecially designed or prepared systems for separating UF6 from carrier gas (hydrogen or helium).Explanatory noteThese systems are designed to reduce the UF6 content in the carrier gas to 1 ppm or less and many incorporate equipment such as:(a) cryogenic heat exchangers and cryoseparators capable of temperatures of -120 °c or less, or(b) cryogenic refrigeration units capable of temperatures of -120 °C or less, or(c) separation nozzle or vortex tube units for the separation of UF6 from carrier gas, or(d) UF6 cold traps capable of temperatures of -20 °C or less.5.6.
\nEspecially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plantsIntroductory noteThe slight difference in mass between the isotopes of uranium causes small changes in chemical reaction equilibria that can be used as a basis for separation of the isotopes. Two processes have been successfully developed: liquid-liquid chemical exchange and solid-liquid ion exchange.In the liquid-liquid chemical exchange process, immiscible liquid phases (aqueous and organic) are countercurrently contacted to give the cascading effect of thousands of separation stages. The aqueous phase consists of uranium chloride in hydrochloric acid solution; the organic phase consists of an extractant containing uranium chloride in an organic solvent.
\nThe contactors employed in the separation cascade can be liquid-liquid exchange columns (such as pulsed columns with sieve plates) or liquid centrifugal contactors. Chemical conversions (oxidation and reduction) are required at both ends of the separation cascade in order to provide for the reflux requirements at each end. A major design concern is to avoid contamination of the process streams with certain metal ions. Plastic, plastic-lined (including use of fluorocarbon polymers) and/or glass-lined columns and piping are therefore used.In the solid-liquid ion-exchange process, enrichment is accomplished by uranium adsorption/desorption on a special, very fast-acting, ion-exchange resin or adsorbent.
\nA solution of uranium in hydrochloric acid and other chemical agents is passed through cylindrical enrichment columns containing packed beds of the adsorbent. For a continuous process, a reflux system is necessary to release the uranium from the adsorbent back into the liquid flow so that `product` and `tails` can be collected. This is accomplished with the use of suitable reduction/oxidation chemical agents that are fully regenerated in separate external circuits and that may be partially regenerated within the isotopic separation columns themselves. The presence of hot concentrated hydrochloric acid solutions in the process requires that the equipment be made of or protected by special corrosion-resistant materials.5.6.1.
\nLiquid-liquid exchange columns (chemical exchange)Countercurrent liquid-liquid exchange columns having mechanical power input (i.e., pulsed columns with sieve plates, reciprocating plate columns, and columns with internal turbine mixers), especially designed or prepared for uranium enrichment using the chemical exchange process. For corrosion resistance to concentrated hydrochloric acid solutions, these columns and their internals are made of or protected by suitable plastic materials (such as fluorocarbon polymers) or glass. The stage residence time of the columns is designed to be short (30 seconds or less).5.6.2. Liquid-liquid centrifugal contactors (chemical exchange)Liquid-liquid centrifugal contactors especially designed or prepared for uranium enrichment using the chemical exchange process.
\nSuch contactors use rotation to achieve dispersion of the organic and aqueous streams and then centrifugal force to separate the phases. For corrosion resistance to concentrated hydrochloric acid solutions, the contactors are made of or are lined with suitable plastic materials (such as fluorocarbon polymers) or are lined with glass. The stage residence time of the centrifugal contactors is designed to be short (30 seconds or less).5.6.3. Uranium reduction systems and equipment (chemical exchange)(a) Especially designed or prepared electrochemical reduction cells to reduce uranium from one valence state to another for uranium enrichment using the chemical exchange process. The cell materials in contact with process solutions must be corrosion resistant to concentrated hydrochloric acid solutions.Explanatory noteThe cell cathodic compartment must be designed to prevent reoxidation of uranium to its higher valence state.
\nTo keep the uranium in the cathodic compartment, the cell may have an impervious diaphragm membrane constructed of special cation exchange material. The cathode consists of a suitable solid conductor such as graphite.(b) Especially designed or prepared systems at the product end of the cascade for taking the U4+ out of the organic stream, adjusting the acid concentration and feeding to the electrochemical reduction cells.Explanatory noteThese systems consist of solvent extraction equipment for stripping the U4+ from the organic stream into an aqueous solution, evaporation and/or other equipment to accomplish solution pH adjustment and control, and pumps or other transfer devices for feeding to the electrochemical reduction cells.
\nA major design concern is to avoid contamination of the aqueous stream with certain metal ions. Consequently, for those parts in contact with the process stream, the system is constructed of equipment made of or protected by suitable materials (such as glass, fluorocarbon polymers, polyphenyl sulfate, polyether sulfone, and resin-impregnated graphite).5.6.4. Feed preparation systems (chemical exchange)Especially designed or prepared systems for producing high-purity uranium chloride feed solutions for chemical exchange uranium isotope separation plants.Explanatory noteThese systems consist of dissolution, solvent extraction and/or ion exchange equipment for purification and electrolytic cells for reducing the uranium U6+ or U4+ to U3+.
\nThese systems produce uranium chloride solutions having only a few parts per million of metallic impurities such as chromium, iron, vanadium, molybdenum and other bivalent or higher multi-valent cations. Materials of construction for portions of the systems processing high-purity U3+ include glass, fluorocarbon polymers, polyphenyl sulfate or polyether sulfone plastic-lined and resin-impregnated graphite.5.6.5. Uranium oxidation systems (chemical exchange)Especially designed or prepared systems for oxidation of U3+ to U4+ for return to the uranium isotope separation cascade in the chemical exchange enrichment process.Explanatory noteThese systems may incorporate equipment such as:(a) equipment for contacting chlorine and oxygen with the aqueous effluent from the isotope separation equipment and extracting the resultant U4+ into the stripped organic stream returning from the product end of the cascade,(b) equipment that separates water from hydrochloric acid so that the water and the concentrated hydrochloric acid may be reintroduced to the process at the proper locations.5.6.6.
\nFast-reacting ion exchange resins/adsorbents (ion exchange)Fast-reacting ion-exchange resins or adsorbents especially designed or prepared for uranium enrichment using the ion exchange process, including porous macroreticular resins, and/or pellicular structures in which the active chemical exchange groups are limited to a coating on the surface of an inactive porous support structure, and other composite structures in any suitable form including particles or fibres. These ion exchange resins/adsorbents have diameters of 0,2 mm or less and must be chemically resistant to concentrated hydrochloric acid solutions as well as physically strong enough so as not to degrade in the exchange columns.
\nThe resins/adsorbents are especially designed to achieve very fast uranium isotope exchange kinetics (exchange rate half-time of less than 10 seconds) and are capable of operating at a temperature in the range of 100 °C to 200 °C.5.6.7. Ion exchange columns (ion exchange)Cylindrical columns greater than 1 000 mm in diameter for containing and supporting packed beds of ion exchange resin/adsorbent, especially designed or prepared for uranium enrichment using the ion exchange process. These columns are made of or protected by materials (such as titanium or fluorocarbon plastics) resistant to corrosion by concentrated hydrochloric acid solutions and are capable of operating at a temperature in the range of 100 °C to 200 °C and pressures above 0,7 MPa (102 psia).5.6.8.
\nIon exchange reflux systems (ion exchange)(a) Especially designed or prepared chemical or electrochemical reduction systems for regeneration of the chemical reducing agent(s) used in ion exchange uranium enrichment cascades.(b) Especially designed or prepared chemical or electrochemical oxidation systems for regeneration of the chemical oxidising agent(s) used in ion exchange uranium enrichment cascades.Explanatory noteThe ion exchange enrichment process may use, for example, trivalent titanium (Ti3+) as a reducing cation in which case the reduction system would regenerate Ti3+ by reducing Ti4+. The process may use, for example, trivalent iron (Fe3+) as an oxidant in which case the oxidation system would regenerate Fe3+ by oxidising Fe2+.5.7.
\nExpecially designed or prepared systems, equipment and components for use in laser-based enrichment plantsIntroductory notePresent systems for enrichment processes using lasers fall into two categories: those in which the process medium is atomic uranium vapour and those in which the process medium is the vapour of a uranium compound. Common nomenclature for such processes include: first category, atomic vapour laser isotope separation (AVLIS or SILVA); second category, molecular laser isotope separation (MLIS or MOLIS) and chemical reaction by isotope selective laser activation (CRISLA). The systems, equipment and components for laser enrichment plants embrace:(a) devices to feed uranium-metal vapour (for selective photo-ionisation) or devices to feed the vapour of a uranium compound (for photo-dissociation or chemical activation);(b) devices to collect enriched and depleted uranium metal as `product` and `tails` in the first category, and devices to collect dissociated or reacted compounds as `product` and unaffected material as `tails` in the second category;(c) process laser systems to selectively excite the uranium-235 species, and (d) feed preparation and product conversion equipment.
\nThe complexity of the spectroscopy of uranium atoms and compounds may require incorporation of any of a number of available laser technologies.Explanatory noteMany of the items listed in this section come into direct contact with uranium metal vapour or liquid or with process gas consisting of UF6 or a mixture of UF6 and other gases. All surfaces that come into contact with the uranium or UF6 are wholly made of or protected by corrosion-resistant materials. For the purposes of the section relating to laser-based enrichment items, the materials resistant to corrosion by the vapour or liquid of uranium metal or uranium alloys include yttria-coated graphite and tantalum; and the materials resistant to corrosion by UF6 include copper, stainless steel, aluminium, aluminium alloys, nickel or alloys containing 60 % or more nickel and UF6-resistant fully fluorinated hydrocarbon polymers.5.7.1.
\nUranium vaporisation systems (AVLIS)Especially designed or prepared uranium vaporisation systems which contain high-power strip or scanning electron beam guns with a delivered power on the target of more than 2,5 kW/cm.5.7.2. Liquid uranium metal handling systems (AVLIS)Especially designed or prepared liquid metal handling systems for molten uranium or uranium alloys, consisting of crucibles and cooling equipment for the crucibles.Explanatory noteThe crucibles and other parts of this system that come into contact with molten uranium and uranium alloys are made of or protected by materials of suitable corrosion and heat resistance. Suitable materials include tantalum, yttria-coated graphite, graphite coated with other rare earth oxides or mixtures thereof.5.7.3.
\nUranium metal `product` and `tails` collector assemblies (AVLIS)Especially designed or prepared `product` and `tails` collector assemblies for uranium metal in liquid or solid form.Explanatory noteComponents for these assemblies are made of or protected by materials resistant to the heat and corrosion of uranium metal vapour or liquid (such as yttria-coated graphite or tantalum) and may include pipes, valves, fittings, `gutters`, feed-throughs, heat exchangers and collector plates for magnetic, electrostatic or other separation methods.5.7.4. Separator module housings (AVLIS)Especially designed or prepared cylindrical or rectangular vessels for containing the uranium metal vapour source, the electron beam gun, and the `product` and `tails` collectors.Explanatory noteThese housings have multiplicity of ports for electrical and water feed-throughs, laser beam windows, vacuum pump connections and instrumentation diagnostics and monitoring.
\nThey have provisions for opening and closure to allow refurbishment of internal components.5.7.5. Supersonic expansion nozzles (MLIS)Especially designed or prepared supersonic expansion nozzles for cooling mixtures of UF6 and carrier gas to 150 K or less and which are corrosion resistant to UF6.5.7.6. Uranium pentafluoride product collectors (MLIS)Especially designed or prepared uranium pentafluoride (UF5) solid product collectors consisting of filter, impact, or cyclone-type collectors, or combinations thereof, and which are corrosion resistant to the UF5/UF6 environment.5.7.7. UF6/carrier gas compressors (MLIS)Especially designed or prepared compressors for UF6/carrier gas mixtures, designed for long term operation in a UF6 environment.
\nThe components of these compressors that come into contact with process gas are made of or protected by materials resistant to corrosion by UF6.5.7.8. Rotary shaft seals (MLIS)Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor rotor with the driver motor so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or seal gas into the inner chamber of the compressor which is filled with a UF6/carrier gas mixture.5.7.9. Fluorination systems (MLIS)Especially designed or prepared systems for fluorinating UF5 (solid) to UF6 (gas).Explanatory noteThese systems are designed to fluorinate the collected UF5 powder to UF6 for subsequent collection in product containers or for transfer as feed to MLIS units for additional enrichment.
\nIn one approach, the fluorination reaction may be accomplished within the isotope separation system to react and recover directly off the `product` collectors. In another approach, the UF5 powder may be removed/transferred from the `product` collectors into a suitable reaction vessel (e.g., fluidised-bed reactor, screw reactor or flame tower) for fluorination. In both approaches, equipment for storage and transfer of fluorine (or other suitable fluorinating agents) and for collection and transfer of UF6 are used.5.7.10. UF6 mass spectrometers/ion sources (MLIS)Especially designed or prepared magnetic or quadrupole mass spectrometers capable of taking `on-line` samples of feed, `product` or `tails`, from UF6 gas streams and having all of the following characteristics:1. unit resolution for mass greater than 320;2. ion sources constructed of or lined with nichrome or monel or nickel plated;3. electron bombardment ionisation sources;4. collector system suitable for isotopic analysis.5.7.11.
\nFeed systems/product and tails withdrawal systems (MLIS)Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including:(a) feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process;(b) desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating;(c) solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form;(d) `product` or `tails` stations used for transferring UF6 into containers.5.7.12. UF6/carrier gas separation systems (MLIS)Especially designed or prepared process systems for separating UF6 from carrier gas.
\nThe carrier gas may be nitrogen, argon, or other gas.Explanatory noteThese systems may incorporate equipment such as:(a) cryogenic heat exchangers or cryoseparators capable of temperatures of -120 °C or less, or(b) cryogenic refrigeration units capable of temperatures of -120 °C or less, or(c) UF6 cold traps capable of temperatures of -20 °C or less.5.7.13. Laser systems (AVLIS, MLIS and CRISLA)Lasers or laser systems especially designed or prepared for the separation of uranium isotopes.Explanatory noteThe laser system for the AVLIS process usually consists of two lasers: a copper vapour laser and a dye laser. The laser system for MLIS usually consists of a CO2 or excimer laser and a multipass optical cell with revolving mirrors at both ends.
\nLasers or laser systems for both processes require a spectrum frequency stabiliser for operation over extended periods of time.5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plantsIntroductory noteIn the plasma separation process, a plasma of uranium ions passes through an electric field tuned to the U-235 ion resonance frequency so that they preferentially absorb energy and increase the diameter of their corkscrew-like orbits. Ions with a large-diameter path are trapped to produce a product enriched in U-235. The plasma, which is made by ionising uranium vapour, is contained in a vacuum chamber with a high-strength magnetic field produced by a superconducting magnet.
\nThe main technological systems of the process include the uranium plasma generation system, the separator module with superconducting magnet and metal removal systems for the collection of `product` and `tails`.5.8.1. Microwave power sources and antennaeEspecially designed or prepared microwave power sources and antennae for producing or accelerating ions and having the following characteristics: greater than 30 GHz frequency and greater than 50 kW mean power output for ion production.5.8.2. Ion excitation coilsEspecially designed or prepared radio frequency ion excitation coils for frequencies of more than 100 kHz and capable of handling more than 40 kW mean power.5.8.3. Uranium plasma generation systemsEspecially designed or prepared systems for the generation of uranium plasma, which may contain high-power strip or scanning electron beam guns with a delivered power on the target of more than 2,5 kW/cm.5.8.4.
\nLiquid uranium metal handling systemsEspecially designed or prepared liquid metal handling systems for molten uranium or uranium alloys, consisting of crucibles and cooling equipment for the crucibles.Explanatory noteThe crucibles and other parts of this system that come into contact with molten uranium or uranium alloys are made of or protected by materials of suitable corrosion and heat resistance. Suitable materials include tantalum, yttria-coated graphite, graphite coated with other rare earth oxides or mixtures thereof.5.8.5. Uranium metal `product` and `tails` collector assembliesEspecially designed or prepared `product` and `tails` collector assemblies for uranium metal in solid form.
\nThese collector assemblies are made of or protected by materials resistant to the heat and corrosion of uranium metal vapour, such as yttria-coated graphite or tantalum.5.8.6. Separator module housingsCylindrical vessels especially designed or prepared for use in plasma separation enrichment plants for containing the uranium plasma source, radio-frequency drive coil and the `product` and `tail` collectors.Explanatory noteThese housings have a multiplicity of ports for electrical feed-throughs, diffusion pump connections and instrumentation diagnostics and monitoring. They have provisions for opening and closure to allow for refurbishment of internal components and are constructed of a suitable non-magnetic material such as stainless steel.5.9.
\nEspecially designed or prepared systems, equipment and components for use in electromagnetic enrichment plantsIntroductory noteIn the electromagnetic process, uranium metal ions produced by ionisation of a salt feed material (typically UCl4) are accelerated and passed through a magnetic field that has the effect of causing the ions of different isotopes to follow different paths. The major components of an electromagnetic isotope separator include: a magnetic field for ion-beam diversion/separation of the isotopes, an ion source with its acceleration system, and a collection system for the separated ions. Auxiliary systems for the process include the magnet power supply system, the ion source high-voltage power supply system, the vacuum system, and extensive chemical handling systems for recovery of product and cleaning/recycling of components.5.9.1.
\nElectromagnetic isotope separatorsElectromagnetic isotope separators, especially designed or prepared for the separation of uranium isotopes, and equipment and components therefor, including:(a) ion sourcesEspecially designed or prepared single or multiple uranium ion sources consisting of a vapour source, ioniser, and beam accelerator, constructed of suitable materials such as graphite, stainless steel, or copper, and capable of providing a total ion beam current of 50 mA or greater;(b) ion collectorsCollector plates consisting of two or more slits and pockets especially designed or prepared for collection of enriched and depleted uranium ion beams and constructed of suitable materials such as graphite or stainless steel;(c) vacuum housingsEspecially designed or prepared vacuum housings for uranium electromagnetic separators, constructed of suitable non-magnetic materials such as stainless steel and designed for operation at pressures of 0,1 Pa or lower;Explanatory noteThe housings are specially designed to contain the ion sources, collector plates and water-cooled liners and have provision for diffusion pump connections and opening and closure for removal and reinstallation of these components.(d) Magnet pole piecesEspecially designed or prepared magnet pole pieces having a diameter greater than 2 m used to maintain a constant magnetic field within a electromagnetic isotope separator and to transfer the magnetic field between adjoining separators.5.9.2.
\nHigh voltage power suppliesEspecially designed or prepared high-voltage power supplies for ion sources, having all of the following characteristics: capable of continuous operation, output voltage of 20 000 V or greater, output current of 1 A or greater, and voltage regulation of better than 0,01 % over a period of eight hours.5.9.3. Magnet power suppliesEspecially designed or prepared high-power, direct current magnet power supplies having all of the following characteristics: capable of continuously producing a current output of 500 A or greater at a voltage of 100 V or greater and with a current or voltage regulation better than 0,01 % over a period of 8 hours.6. PLANTS FOR THE PRODUCTION OF HEAVY WATER, DEUTERIUM AND DEUTERIUM COMPOUNDS AND EQUIPMENT ESPECIALLY DESIGNED OR PREPARED THEREFORIntroductory noteHeavy water can be produced by a variety of processes.
\nHowever, the two processes that have proven to be commercially viable are the water-hydrogen sulphide exchange process (GS process) and the ammonia-hydrogen exchange process.The GS process is based upon the exchange of hydrogen an deuterium between water and hydrogen sulphide within a series of towers which are operated with the top section cold and the bottom section hot. Water flows down the towers while the hydrogen sulphide gas circulates from the bottom to the top of the towers. A series of perforated trays are used to promote mixing between the gas and the water. Deuterium migrates to the water at low temperatures and to the hydrogen sulphide at high temperatures. Gas or water, enriched in deuterium, is removed from the first stage towers at the junction of the hot and cold sections and the process is repeated in subsequent stage towers.
\nThe product of the last stage, water enriched up to 30 % in deuterium, is sent to a distillation unit to produce reactor grade heavy water, i.e., 99,75 % deuterium oxide.The ammonia-hydrogen exchange process can extract deuterium from synthesis gas through contact with liquid ammonia in the presence of a catalyst. The synthesis gas is fed into exchange towers and to an ammonia converter. Inside the towers the gas flows from the bottom to the top while the liquid ammonia flows from the top to the bottom. The deuterium is stripped from the hydrogen in the synthesis gas and concentrated in the ammonia. The ammonia then flows into an ammonia cracker at the bottom of the tower while the gas flows into an ammonia converter at the top.
\nFurther enrichment takes place in subsequent stages and reactor grade heavy water is produced through final distillation. The synthesis gas feed can be provided by an ammonia plant that, in turn, can be constructed in association with a heavy water ammonia-hydrogen exchange plant. The ammonia-hydrogen exchange process can also use ordinary water as a feed source of deuterium.Many of the key equipment items for heavy water production plants using GS or the ammonia-hydrogen exchange processes are common to several segments of the chemical and petroleum industries. This is particularly so for small plants using the GS process. However, few of the items are available `off-the shelf`. The GS and ammonia-hydrogen processes require the handling of large quantities of flammable, corrosive and toxic fluids at elevated pressures.
\nAccordingly, in establishing the design and operating standards for plants and equipment using these processes, careful attention to the materials selection and specifications is required to ensure long service life with high safety and reliability factors. The choice of scale is primarily a function of economics and need. Thus, most of the equipment items would be prepared according to the requirements of the customer.Finally, it should be noted that, in both the GS and the ammonia-hydrogen exchange processes, items of equipment which individually are not especially designed or prepared for heavy water production can be assembled into systems which are especially designed or prepared for producing heavy water.
\nThe catalyst production system used in the ammonia-hydrogen exchange process and water distillation systems used for the final concentration of heavy water to reactor-grade in either process are examples of such systems.The items of equipment which are especially designed or prepared for the production of heavy water utilising either the water-hydrogen sulphide exchange process or the ammonia-hydrogen exchange process include the following:6.1. Water - hydrogen sulphide exchange towersExchange towers fabricated from fine carbon steel (such as ASTM A516) with diameters of 6 m (20') to 9 m (39'), capable of operating at pressures greater than or equal to 2 MPa (300 psi) and with a corrosion allowance of 6 mm or greater, especially designed or prepared for heavy water production utilising the water-hydrogen sulphide exchange process.6.2.
\nBlowers and compressorsSingle stage, low head (i.e., 0,2 MPa or 30 psi) centrifugal blowers or compressors for hydrogen-sulphide gas circulation (i.e., gas containing more than 70 % H2S) especially designed or prepared for heavy water production utilising the water-hydrogen sulphide exchange process. These blowers or compressors have a throughput capacity greater than or equal to 56 m3/second (120,000 SCFM) while operating at pressures greater than or equal to 1,8 MPa (260 psi) suction and have seals designed for wet H2S service.6.3. Ammonia-hydrogen exchange towersAmmonia-hydrogen exchange towers greater than or equal to 35 m (114,3' in height with diameters of 1,5 m (4,9' to 2,5 m (8,2') capable of operating at pressures greater than 15 MPa (2225 psi) especially designed or prepared for heavy water production utilising the ammonia-hydrogen exchange process.
\nThese towers also have at least one flanged axial opening of the same diameter as the cylindrical part through which the tower internals can be inserted or withdrawn.6.4. Tower internals and stage pumpsTower internals and stage pumps especially designed or prepared for towers for heavy water production utilising the ammonia-hydrogen exchange process. Tower internals include especially designed stage contactors which promote intimate gas/liquid contact. Stage pumps include especially designed submersible pumps for circulation of liquid ammonia within a contacting stage internal to the stage towers.6.5. Ammonia crackersAmmonia crackers with operating pressures greater than or equal to 3 MPa (450 psi) especially designed or prepared for heavy water production utilising the ammonia-hydrogen exchange process.6.6.
\nInfrared absorption analysersInfrared absorption analysers capable of on-line hydrogen/deuterium ratio analysis where deuterium concentrations are equal to or greater than 90 %.6.7. Catalytic burnersCatalytic burners for the conversion of enriched deuterium gas into heavy water especially designed or prepared for heavy water production utilising the ammonia-hydrogen exchange process.7. PLANTS FOR THE CONVERSION OF URANIUM AND EQUIPMENT ESPECIALLY DESIGNED OR PREPARED THEREFORIntroductory noteUranium conversion plants and systems may perform one or more transformations from one uranium chemical species to another, including: conversion of uranium ore concentrates to UO3, conversion of UO3 to UO2, conversion of uranium oxides to UF4 or UF6, conversion of UF4 to UF6, conversion of UF6 to UF4, conversion of UF4 to uranium metal, and conversion of uranium fluorides to UO2.
\nMany of the key equipment items for uranium conversion plants are common to several segments of the chemical process industry. For example, the types of equipment employed in these processes may include: furnaces, rotary kilns, fluidised bed reactors, flame tower reactors, liquid centrifuges, distillation columns and liquid-liquid extraction columns. However, few of the items are available `off-the-shelf`, most would be prepared according to the requirements and specifications of the customer. In some instances, special design and construction considerations are required to address the corrosive properties of some of the chemicals handled (HF, F2, CIF3, and uranium fluorides). Finally, it should be noted that, in all of the uranium conversion processes, items of equipment which individually are not especially designed or prepared for uranium conversion can be assembled into systems which are especially designed or prepared for use in uranium conversion.7.1.
\nEspecially designed or prepared systems for the conversion of uranium ore concentrates to UO3Explanatory noteConversion of uranium ore concentrates to UO3 can be performed by first dissolving the ore in nitric acid and extracting purified uranyl nitrate using a solvent such as tributyl phosphate. Next, the uranyl nitrate is converted to UO3 either by concentration and denitration or by neutralization with gaseous ammonia to produce ammonium diuranate with subsequent filtering, drying, and calcining.7.2. Especially designed or prepared systems for the conversion of UO3 to UF6Explanatory noteConversion of UO3 to UF6 can be performed directly by fluorination. The process requires a source of fluorine gas or chlorine trifluoride.7.3.
\nEspecially designed or prepared systems for the conversion of UO3 to UO2Explanatory noteConversion of UO3 to UO2 can be performed through reduction of UO3 with cracked ammonia gas or hydrogen.7.4. Especially designed or prepared systems for the conversion of UO2 to UF4Explanatory noteConversion of UO2 to UF4 can be performed by reacting UO2 with hydrogen fluoride gas (HF) at 300-500 °C.7.5. Especially designed or prepared systems for the conversion of UF4 to UF6Explanatory noteConversion of UF4 to UF6 is performed by exothermic reaction with fluorine in a tower reactor. UF6 is condensed from the hot effluent gases by passing the effluent stream through a cold trap cooled to -10 °C. The process requires a source of fluorine gas.7.6.
\nEspecially designed or prepared systems for the conversion of UF4 to U metalExplanatory noteConversion UF4 to U metal is performed by reduction with magnesium (large batches) or calcium (small batches). The reaction is carried out at temperatures above the melting point of uranium (1 130 °C).7.7. Especially designed or prepared systems for the conversion of UF6 to UO2Explanatory noteConversion of UF6 to UO2 can be performed by one of three processes. In the first, UF6 is reduced and hydrolysed to UO2 using hydrogen and steam. In the second, UF6 is hydrolysed by solution in water, ammonia is added to precipitate ammonium diuranate, and the diuranate is reduced to UO2 with hydrogen at 820 °C.
\nIn the third process, gaseous UF6, CO2 and NH3 are combined in water, precipitating ammonium uranyl carbonate. The ammonium aranyl carbonate is combined with steam and hydrogen at 500-600 °C to yield UO2.UF6 to UO2 conversion is often performed as the first stage of a fuel fabrication plant.7.8. Especially designed or prepared systems for the conversion of UF6 to UF4Explanatory noteConversion of UF6 to UF4 is performed by reduction with hydrogen.Annex IIITo the extent that the measures in this Protocol involve nuclear material declared by the Community and without prejudice to Article 1 of this Protocol, the Agency and the Community shall cooperate to facilitate implementation of those measures and shall avoid unnecessary duplication of activities.The Community shall provide the Agency with information relating to transfers, for both nuclear and non-nuclear purposes, from each State to another Member State of the Community and to such transfers to each State from another Member State of the Community that corresponds to the information to be provided under Article 2 (a)(vi)(b) and under Article 2(a)(vi)(c) in relation to exports and imports of source material which has not reached the composition and purity suitable for fuel fabrication or for being isotopically enriched.Each State shall provide the Agency with information relating to transfers to or from another Member State of the Community that corresponds to the information on specified equipment and non-nuclear material listed in Annex II of this Protocol to be provided under Article 2(a)(ix)(a) in relation to exports and, on specific request of the Agency, under Article 2(a)(ix)(b) in relation to imports.With regard to the Community's Joint Research Centre, the Community shall also implement the measures which this Protocol sets out for States, as appropriate in close collaboration with the State on whose territory an establishment of the centre is located.The Liaison Committee, established under Article 25(a) of the Protocol referred to in Article 26 of the Safeguards Agreement, will be extended in order to allow for participation by representatives of the States and adjustment to the new circumstances resulting from this Protocol.For the sole purposes of the implementation of this Protocol, and without prejudice to the respective competences and responsibilities of the Community and its Member States, each State which decides to entrust to the Commission of the European Communities implementation of certain provisions which under this Protocol are the responsibility of the States, shall so inform the other Parties to the Protocol through a side letter.
\nThe Commission of the European Communities shall inform the other Parties to the Protocol of its acceptance of any such decisions.(*) On 8 June 1998, the Council approved the conclusion by the Commission on behalf of the European Atomic Energy Community (the Community) not only of this Additional Protocol to the Agreement between the 13 non-nuclear-weapon Member States of the Community, the Community and the IAEA (published in OJ L 51 Volume 21, dated 22 February 1978 and as IAEA document INFCIRC/193, dated 14 September 1973) but also Additional Protocols to the Agreements between the United Kingdom of Great Britain and Northern Ireland, the Community and the IAEA (published as IAEA document INFCIRC/263, dated October 1978) and between France, the Community and the IAEA (published as IAEA document INFCIRC/290, dated December 1981).
\nAll three Additional Protocols were signed by the relevant Parties in Vienna on 22 September 1998. The texts of each Additional Protocol can be accessed at the following internet address: http://europa.eu.int/en/comm/dg17/nuclear/nuchome.htm Līgums starp Beļģijas Karalisti, Dānijas Karalisti, Itālijas Republiku, Īriju, Luksemburgas Lielhercogisti, Nīderlandes Karalisti, Vācijas Federatīvo Republiku, Eiropas Atomenerģijas kopienu (Euratom) un Starptautisko atomenerģijas aģentūru, kas noslēgts, pildot III panta 1. un 4.punktu Līgumā par kodolieroču neizplatīšanu (78/164/Euratom)TĀ KĀ Beļģijas Karaliste, Dānijas Karaliste, Itālijas Republika, Īrija, Luksemburgas Lielhercogiste, Nīderlandes Karaliste un Vācijas Federatīvā Republika (še turpmāk \"valstis\") ir parakstījušas Līgumu par kodolieroču neizplatīšanu (še turpmāk \"līgums\"), kas bija pieejams parakstīšanai Londonā, Maskavā un Vašingtonā 1968.gada 1.jūlijā un stājās spēkā 1970.gada 5.martā;ŅEMOT VĒRĀ, ka, ievērojot līguma IV panta 1.punktu, līgumā nekas nav interpretējams tā, ka skar visu līgumslēdzēju pušu neatņemamās tiesības attīstīt kodolenerģijas pētniecību, ražošanu un izmantošanu mierīgiem nolūkiem bez diskriminācijas un atbilstīgi līguma I un II pantam;ŅEMOT VĒRĀ, ka saskaņā ar līguma IV panta 2.punktu visas līgumslēdzējas puses apņemas atvieglot iespējami pilnīgāko iekārtu, materiālu un zinātniskās un tehniskās informācijas apmaiņu un piedalīties tajā, lai kodolenerģiju izmantotu mierīgiem nolūkiem;ŅEMOT VĒRĀ arī to, ka saskaņā ar tā paša punkta noteikumiem līgumslēdzējas puses, uz ko tas attiecas, atsevišķi vai kopā sadarbojas arī ar citām valstīm vai starptautiskām organizācijām, lai turpinātu izstrādāt kodolenerģijas lietojumus mierīgiem nolūkiem, īpaši to valstu teritorijā, kurām nav kodolieroču un kuras ir līgumslēdzējas puses;TĀ KĀ līguma III panta 1.punktā ir paredzēts, ka visas valstis, kam nav kodolieroču un kas ir līgumslēdzējas puses, apņemas akceptēt garantijas, kuras noteiktas apspriežamā un noslēdzamā līgumā ar Starptautisko atomenerģijas aģentūru (še turpmāk \"aģentūra\") saskaņā ar aģentūras statūtiem (še turpmāk \"statūti\") un aģentūras garantiju sistēmu, kuras vienīgais nolūks ir pārbaudīt to saistību izpildi, kuras uzliek šis līgums, un novērst kodolenerģijas novirzīšanu no mierīgiem lietojumiem uz kodolieročiem vai citām kodolsprādzienierīcēm;TĀ KĀ III panta 4.punktā paredzēts, ka valstis, kam nav kodolieroču un kas ir līgumslēdzējas puses, slēdz līgumus ar aģentūru, lai izpildītu minētā panta prasības atsevišķi vai kopā ar citām valstīm saskaņā ar statūtiem;TĀ KĀ valstis ir Eiropas Atomenerģijas kopienas (Euratom) (še turpmāk \"Kopiena\") dalībvalstis un ir piešķīrušas regulējošas, izpildu un tiesu pilnvaras iestādēm, kas ir kopīgas Eiropas Kopienām, un šīs iestādes tās patstāvīgi realizē savas kompetences jomā, un tās var tieši stāties spēkā dalībvalstu tiesību sistēmā;TĀ KĀ šajā iestāžu sistēmā Kopienas īpašais uzdevums ir ar attiecīgām garantijām nodrošināt to, ka kodolmateriālus nenovirza mērķiem, kas nav mērķi, kuriem tie paredzēti, un no līguma spēkā stāšanās brīža valstu teritorijā tai ar Euratom Līgumā noteikto garantiju sistēmu nodrošināt to, ka valstu teritorijā izejmateriālu un īpašo skaldmateriālu mierīgā kodoldarbībā nenovirza kodolieročiem vai citām kodolsprādzienierīcēm;TĀ KĀ šīs garantijas ietver paziņošanu Kopienai par kodoliekārtu galvenajiem tehniskajiem raksturlielumiem, uzskaites dokumentu kārtošanu un iesniegšanu, kas Kopienā ļauj uzskaitīt kodolmateriālus kopumā, inspicēšanu, kuru veic Kopienas amatpersonas, un sankciju sistēmu;TĀ KĀ Kopienas uzdevums ir dibināt attiecības ar citām valstīm un starptautiskām organizācijām, kas var veicināt kodolenerģijas izmantošanu mierīgiem nolūkiem, un tā ir skaidri pilnvarota uzņemties īpašas garantiju saistības līgumā ar trešo valsti vai starptautisku organizāciju;TĀ KĀ aģentūras starptautisko garantiju sistēma, kas minēta līgumā, ietver īpaši noteikumus par projekta informācijas iesniegšanu aģentūrai, uzskaites kārtošanu, ziņojumu iesniegšanu par visu kodolmateriālu, uz kuru attiecas aģentūrai dotās garantijas, inspekcijas, ko veic aģentūras inspektori, prasības valsts kodolmateriāla uzskaites un kontroles sistēmas izveidei un uzturēšanai un pasākumus, kuri attiecas uz nenovirzīšanas pārbaudi;TĀ KĀ aģentūrai saskaņā ar saviem statūtos noteiktajiem pienākumiem un savām attiecībām ar Apvienoto Nāciju Organizācijas Ģenerālo Asambleju un Drošības Padomi jāpārliecina starptautiskā sabiedrība par to, ka saskaņā ar līgumu piemēro efektīvas garantijas;NORĀDOT, ka valstis, kas līguma parakstīšanas brīdī ir bijušas Kopienas dalībvalstis, parakstot darījušas zināmu to, ka garantijas, kuras paredzētas līguma III panta 1.punktā, jānoteic pārbaužu līgumā starp Kopienu, valstīm un aģentūru un jāformulē tā, lai neskar valstu un Kopienas tiesības un pienākumus;TĀ KĀ aģentūras augstākā valde (še turpmāk \"valde\") ir apstiprinājusi pilnīgu noteikumu struktūras un satura paraugu līgumiem starp aģentūru un valstīm, kas saskaņā ar līgumu jāizmanto par pamatu sarunām par garantiju līgumiem starp aģentūru un valstīm, kurām nav kodolieroču un kuras ir līgumslēdzējas puses;TĀ KĀ saskaņā ar statūtu III panta A) punkta 5.apakšpunktu aģentūra ir pilnvarota pēc līgumslēdzēju pušu pieprasījuma piemērot garantijas jebkuras divpusējas vai daudzpusējas vienošanās gadījumā vai pēc kādas valsts pieprasījuma jebkurām šīs valsts darbībām atomenerģētikas jomā;TĀ KĀ aģentūras, Kopienas un valstu interesēs ir novērst nevajadzīgu garantijas pasākumu pārklāšanos,AĢENTŪRA, KOPIENA UN VALSTIS IR VIENOJUŠĀS PAR TURPMĀKO.I DAĻAPAMATVIENOŠANĀS1.pantsIevērojot līguma III panta 1.punktu, valstis vienojas par to, ka saskaņā ar šā līguma noteikumiem tās akceptē garantijas, kas attiecas uz visu izejmateriālu un īpašo skaldmateriālu visās mierīgās kodoldarbībās savā teritorijā un savā jurisdikcijā vai kodoldarbībās, kuras to kontrolē notiek citur, ar vienīgo nolūku, lai pārbaudītu, vai šādu materiālu nenovirza kodolieročiem vai citām kodolsprādzienierīcēm.GARANTIJU PIEMĒROŠANA2.pantsAģentūrai ir tiesības un pienākums nodrošināt to, ka garantijas saskaņā ar šā līguma noteikumiem piemēro visam izejmateriālam vai īpašajam skaldmateriālam visās mierīgās kodoldarbībās valstu teritorijā to jurisdikcijā vai kodoldarbībās, kuras to kontrolē notiek citur, ar vienīgo nolūku, lai pārbaudītu, vai šādu materiālu nenovirza kodolieročiem vai citām kodolsprādzienierīcēm.3.pantsa) Kopiena apņemas, piemērojot savas garantijas par izejmateriālu un īpašo skaldmateriālu visās mierīgās kodoldarbībās valstu teritorijā, sadarboties ar aģentūru saskaņā ar šā līguma noteikumiem, lai konstatētu, ka šādu izejmateriālu un īpašo skaldmateriālu nenovirza kodolieročiem vai citām kodolsprādzienierīcēm.b) aģentūra piemēro savas garantijas saskaņā ar šā līguma noteikumiem tā, lai tā var pārbaudīt un konstatēt, ka kodolmateriāls no mierīgiem lietojumiem nav novirzīts kodolieročiem vai citām kodolsprādzienierīcēm, un saskaņā ar Kopienas garantiju sistēmas secinājumiem.
\nAģentūras pārbaudē cita starpā iekļauj neatkarīgus mērījumus un novērojumus, ko aģentūra izdara saskaņā ar procedūrām, kuras noteiktas šajā līgumā. Aģentūra savā pārbaudē pienācīgi ņem vērā Kopienas garantiju sistēmas efektivitāti saskaņā ar šā līguma noteikumiem.SADARBĪBA STARP AĢENTŪRU, KOPIENU UN VALSTĪM4.pantsAģentūra, Kopiena un valstis sadarbojas, ciktāl šajā līgumā paredzēto garantiju realizācijas veicināšana attiecas uz katru līgumslēdzēju pusi, un novērš nevajadzīgu garantijas darbību pārklāšanos.GARANTIJU REALIZĀCIJA5.pantsŠajā līgumā paredzētās garantijas realizē tā, lai:a) novērstu ekonomikas un tehnikas attīstības kavēšanu Kopienā vai starptautiskās sadarbības kavēšanu mierīgo kodoldarbību jomā, ieskaitot kodolmateriāla starptautisko apmaiņu;b) novērstu neadekvātu iejaukšanos mierīgajās kodoldarbībās Kopienā un īpaši iekārtu darbībā; unc) konsekventi ievērotu piesardzīgas vadības praksi, kas vajadzīga, lai kodoldarbības veiktu ekonomiski un droši.6.pantsa) Aģentūra veic visus piesardzības pasākumus, lai aizsargātu komerciālos un rūpnieciskos noslēpumus un citu konfidenciālo informāciju, ko tā iegūst, pildot šo līgumu.b) i) Aģentūra nepublicē vai nepaziņo nevienai valstij, organizācijai vai personai informāciju, ko tā iegūst saistībā ar šā līguma izpildi, izņemot gadījumu, kad specifisku informāciju, kura attiecas uz tā izpildi, drīkst sniegt valdei un tiem aģentūras štata locekļiem, kam šāda informācija vajadzīga viņu oficiālo pienākumu izpildei saistībā ar garantijām, bet tikai tādā mērā, kādā tas vajadzīgs, lai aģentūra izpildītu savus pienākumus šā līguma izpildē.ii) Informācijas kopsavilkumu par kodolmateriālu, uz ko attiecas garantijas saskaņā ar šo līgumu, drīkst publicēt ar valdes lēmumu, ja tieši ieinteresētās valstis vai Kopiena, ciktāl tas attiecas uz katru no līgumslēdzējām pusēm atsevišķi, tam piekrīt.7.pantsa) Realizējot garantijas saskaņā ar šo līgumu, pilnīgi ievēro tehnikas attīstību jomā, uz ko attiecas garantijas, un dara visu, lai nodrošinātu optimālu izmaksu lietderību un tās kodolmateriāla plūsmas efektīvas garantēšanas principa piemērošanu, uz kuru attiecas garantijas saskaņā ar šo līgumu, izmantojot līdzekļus un citas metodes noteiktos stratēģiskos punktos tādā mērā, kādā tagadējā vai vēlāka laika tehnoloģija ļauj.b) Lai nodrošinātu optimālu izmaksu lietderību, izmanto tādus līdzekļus kā:i) norobežojumu kā līdzekli materiālu bilances noteikšanai uzskaites nolūkos;ii) statistikas metodes un paraugu ņemšanu izlases kārtā kodolmateriāla plūsmas vērtēšanai; uniii) pārbaudes procedūru koncentrēšanu uz tām kodoldegvielas cikla stadijām, kas saistītas ar tā kodolmateriāla ražošanu, pārstrādi, lietošanu vai glabāšanu, no kura varētu viegli izgatavot kodolieročus vai citas kodolsprādzienierīces, un pārbaudes procedūru samazināšanu līdz minimumam attiecībā uz kodolmateriālu, ar nosacījumu, ka tas netraucē izpildīt šo līgumu.INFORMĀCIJAS SNIEGŠANA AĢENTŪRAI8.pantsa) Lai nodrošinātu efektīvu garantiju realizēšanu saskaņā ar šo līgumu, Kopiena saskaņā ar šā līguma noteikumiem sniedz aģentūrai informāciju par kodolmateriālu, uz ko attiecas šādas garantijas, un par to iekārtu funkcijām, kurām ir nozīme garantiju realizēšanā attiecībā uz šādu materiālu.b) i) Aģentūra pieprasa tikai obligāto informācijas un datu daudzumu, kas vajadzīgs, lai tā izpildītu savus pienākumus saskaņā ar šo līgumu.ii) Informācija, kas attiecas uz iekārtām, ir obligātā informācija, kura vajadzīga, lai saskaņā ar šo līgumu realizētu garantijas attiecībā uz kodolmateriālu.c) Pēc Kopienas lūguma aģentūra ir gatava Kopienas telpās izskatīt projekta informāciju, ko Kopiena uzskata par īpaši konfidenciālu. Šāda informācija nav fiziski jāpārraida uz aģentūru, ja tā paliek viegli pieejama turpmākai aģentūras izskatīšanai Kopienas telpās.AĢENTŪRAS INSPEKTORI9.pantsa) i) Aģentūra nodrošina Kopienas un valstu piekrišanu aģentūras inspektoru norīkošanai uz valstīm.ii) Ja Kopiena norīkošanas priekšlikuma brīdī vai pēc norīkošanas iebilst pret norīkojumu, tad aģentūra dod priekšlikumu Kopienai un valstīm par alternatīvu norīkojumu/alternatīviem norīkojumiem.iii) Ja tādēļ, ka Kopiena atkārtoti atsakās akceptēt aģentūras inspektoru norīkojumu, inspekcijas, kas jāveic saskaņā ar šo līgumu, tiek traucētas, tad šādu atteikumu izskata valde pēc aģentūras ģenerāldirektora (še turpmāk \"ģenerāldirektors\") ierosinājuma, lai pieņemtu attiecīgu lēmumu.b) Kopiena un attiecīgās valstis veic pasākumus, kas vajadzīgi, lai nodrošinātu to, ka aģentūras inspektori var efektīvi pildīt savas funkcijas saskaņā ar šo līgumu.c) Aģentūras inspektoru apmeklējumi un darbības jāsaskaņo tā, lai:i) līdz minimumam samazinātu iespējamās neērtības un traucējumus Kopienai, valstīm un inspicējamām mierīgajām kodoldarbībām; unii) nodrošinātu rūpniecisko noslēpumu vai jebkuras citas tādas konfidenciālas informācijas aizsardzību, ko iegūst aģentūras inspektori.PRIVILĒĢIJAS UN NEAIZSKARAMĪBA10.pantsVisas valstis aģentūrai, arī tās īpašumam, līdzekļiem un aktīviem, tās inspektoriem un citām amatpersonām, kas pilda savas funkcijas saskaņā ar šo līgumu, piemēro attiecīgos noteikumus, kuri ir līgumā attiecībā uz Starptautiskās atomenerģijas aģentūras privilēģijām un neaizskaramību.KODOLMATERIĀLA PATĒRIŅŠ VAI ATŠĶAIDĪJUMS11.pantsSaskaņā ar šo līgumu garantijas, kas attiecas uz kodolmateriālu, beidzas, kad Kopiena un aģentūra konstatē, ka materiāls ir patērēts vai atšķaidīts tā, ka vairs nav lietojams nevienai kodoldarbībai, uz kuru attiecas garantijas, vai ir kļuvis faktiski neatgūstams.KODOLMATERIĀLA NODOŠANA ĀRPUS VALSTĪM12.pantsKopiena saskaņā ar šā līguma noteikumiem paziņo aģentūrai par tā kodolmateriāla nodošanu ārpus valstīm, uz kuru attiecas garantijas.
\nGarantijas, kas saskaņā ar šo līgumu attiecas uz kodolmateriālu, beidzas, kad saņēmējvalsts par to ir uzņēmusies atbildību, kas paredzēta šajā līgumā. Aģentūra uzskaita katru nodošanas gadījumu un pēc vajadzības garantiju atkārtoto piemērošanu nodotajam kodolmateriālam.NOTEIKUMI, KAS ATTIECAS UZ KODOLMATERIĀLU, KAS IZMANTOJAMS AR KODOLENERĢIJU NESAISTĪTĀS DARBĪBĀS13.pantsJa kodolmateriāls, uz ko saskaņā ar šo līgumu attiecas garantijas, jāizmanto tādās ar kodolenerģiju nesaistītās darbībās kā sakausējumu vai keramikas ražošanā, tad Kopiena pirms šādas materiāla izmantošanas vienojas ar aģentūru par apstākļiem, kādos var izbeigt garantijas, kuras saskaņā ar šo līgumu attiecas uz šādu materiālu.GARANTIJU NEPIEMĒROŠANA KODOLMATERIĀLAM, KAS IZMANTOJAMS DARBĪBĀS, KURAS NAV MIERĪGAS DARBĪBAS14.pantsJa valsts plāno īstenot virzību uz tāda kodolmateriāla izmantošanu, kam saskaņā ar šo līgumu jāpiemēro garantijas, tādā kodoldarbībā, kurai saskaņā ar šo līgumu nav jāpiemēro garantijas, tad piemēro šādas procedūras:a) Kopiena un valsts informē aģentūru par darbību, un valsts izskaidro:i) ka kodolmateriāla izmantošana neparedzētā militārā darbībā nav pretrunā tam, ka valsts var būt apņēmusies kodolmateriālu izmantot tikai mierīgā kodoldarbībā, uz ko arī attiecas aģentūras garantijas; unii) ka garantiju nepiemērošanas periodā saskaņā ar šo līgumu kodolmateriālu neizmanto kodolieroču vai citu kodolsprādzienierīču ražošanai;b) aģentūra un Kopiena vienojas par to, ka šajā līgumā paredzētās garantijas nepiemēro tikai laikā, kad kodolmateriālu izmanto šādā darbībā.
\nVienojoties pēc iespējas nosaka periodu vai apstākļus, kuros šādas garantijas nepiemēro. Jebkurā gadījumā šajā līgumā paredzētās garantijas atkal piemēro, tiklīdz kodolmateriāls atgriežas mierīgā kodoldarbībā. Aģentūru pastāvīgi informē par šāda materiāla kopējo daudzumu attiecīgajā valstī vai attiecīgajās valstīs un sastāvu, kā arī par jebkuru šāda materiāla nodošanu no attiecīgās valsts vai attiecīgajām valstīm; unc) katra vienošanās jāsaskaņo ar aģentūru. Šāds saskaņojums jādod pēc iespējas ātri, un tam jāattiecas tikai uz tādiem jautājumiem kā, cita starpā, laika, procedūras un ziņošanas noteikumiem, bet tajā neietver nekādu apstiprinājumu vai konfidenciālu informāciju par militāro darbību vai to neattiecina uz kodolmateriāla izmantošanu tajā.FINANSĒJUMS15.pantsAģentūra, Kopiena un valstis sedz izdevumus, kas katrai no tām rodas, pildot pienākumus saskaņā ar šo līgumu.
\nTomēr, ja Kopienai, valstīm vai personām to kompetences robežās rodas ārkārtas izdevumi kāda īpaša aģentūras pieprasījuma dēļ, tad aģentūra šādus izdevumus atmaksā ar noteikumu, ka tā iepriekš piekritusi atmaksāt. Jebkurā gadījumā aģentūra sedz jebkuras tās inspektoru pieprasītas papildu mērīšanas vai paraugu ņemšanas izmaksas.TREŠO PERSONU ATBILDĪBA PAR KODOLKAITĒJUMU16.pantsKopiena un valstis nodrošina to, ka jebkura aizsardzība, ieskaitot jebkuru apdrošināšanu vai citu finansiālu nodrošinājumu pret kodolkaitējumu, ko rada trešās personas, un kura var būt pieejama saskaņā ar to normatīvajiem aktiem, aģentūrai un tās amatpersonām šā līguma izpildes nolūkā ir piemērojama tāpat kā šādu aizsardzību piemēro attiecīgo valstu pilsoņiem.STARPTAUTISKĀ ATBILDĪBA17.pantsJebkuru Kopienas vai kādas valsts prasību pret aģentūru vai aģentūras prasību pret Kopienu vai kādu valsti, kas attiecas uz kaitējumu, kurš radies, realizējot garantijas saskaņā ar šo līgumu, un kurš nav kaitējums, kas radies no kodolincidenta, risina saskaņā ar starptautiskajām tiesībām.PASĀKUMI, KAS ATTIECAS UZ NENOVIRZĪŠANAS PĀRBAUDI18.pantsJa valde pēc ģenerāldirektora ziņojuma nolemj, ka Kopienas vai valsts rīcība, ciktāl tas attiecas uz katru pusi atsevišķi, ir būtiska un steidzama, lai nodrošinātu pārbaudi, vai kodolmateriālu, uz ko saskaņā ar šo līgumu attiecas garantijas, nenovirza kodolieročiem vai citām kodolsprādzienierīcēm, valde var aicināt Kopienu vai valsti bez kavēšanās rīkoties pēc vajadzības neatkarīgi no tā, vai ir izmantotas procedūras domstarpību atrisināšanai, ievērojot 22.pantu.19.pantsJa valde, izskatot attiecīgo informāciju, ko tai paziņojis ģenerāldirektors, secina, ka aģentūra nespēj apstiprināt, ka kodolmateriāls, kam saskaņā ar šo līgumu piemērojamas garantijas, nav novirzīts kodolieročiem vai citām kodolsprādzieniekārtām, tad tā var sagatavot ziņojumus, kuri paredzēti statūtu XII panta C) punktā, un pēc vajadzības veikt arī pārējos pasākumus, kas paredzēti minētajā punktā.
\nTādā gadījumā valde ņem vērā to, kādā mērā piemērotie garantiju pasākumi ir pārliecinoši, un piedāvā Kopienai vai valstij, ciktāl tas attiecas uz katru līgumslēdzēju pusi atsevišķi, visas pieņemamās iespējas sniegt valdei visus vajadzīgos pierādījumus tam, ka piemērotie garantiju pasākumi ir pārliecinoši.LĪGUMA INTERPRETĀCIJA, PIEMĒROŠANA UN DOMSTARPĪBU RISINĀŠANA20.pantsPēc aģentūras, Kopienas vai kādas valsts pieprasījuma apspriež jebkuru jautājumu, kas izriet no šā līguma interpretācijas vai piemērošanas.21.pantsKopienai un valstīm ir tiesības pieprasīt jebkuru jautājumu, kas izriet no šā līguma interpretācijas vai piemērošanas, izskatīt valdē. Valde uzaicina Kopienu un attiecīgo valsti piedalīties jebkura tāda jautājuma apspriešanā valdē.22.pantsJebkuras domstarpības, kas rodas, interpretējot vai piemērojot šo līgumu, izņemot domstarpības, kuras attiecas uz valdes secinājumu saskaņā ar 19.pantu vai valdes rīcību, ievērojot šādu secinājumu, un kas nav atrisinātas sarunās vai pēc citas procedūras, par kuru aģentūra, Kopiena un valstis vienojušās, pēc pieprasījuma, ko kāda no tām iesniedz, domstarpības izskata šķīrējtiesas tribunāls piecu šķīrējtiesnešu sastāvā.
\nDivus šķīrējtiesnešus izraugās Kopiena un valstis un divus — aģentūra, un šie četri šķīrējtiesneši ievēlē piekto, kurš ir priekšsēdētājs.Ja 30 dienās pēc tam, kad ir pieprasīta izskatīšana šķīrējtiesā, Kopiena un valstis vai aģentūra nav izraudzījusies katra divus šķīrējtiesnešus, tad Kopiena vai aģentūra var pieprasīt, lai šos šķīrējtiesnešus norīko Starptautiskās tiesas priekšsēdētājs. Tādu pašu procedūru piemēro, ja trīsdesmit dienās pēc ceturtā šķīrējtiesneša iecelšanas vai norīkošanas nav ievēlēts piektais šķīrējtiesnesis.Šķīrējtiesas tribunāla locekļu vairākums veido kvorumu, un visu lēmumu pieņemšanai ir vajadzīgs vismaz triju šķīrējtiesnešu labvēlīgs balsojums. Šķīrējtiesas procesu nosaka tribunāls.
\nTribunāla lēmumi ir aģentūrai, Kopienai un attiecīgajām valstīm saistoši.PIEVIENOŠANĀS23.pantsa) Šis līgums stājas spēkā attiecībā uz valstīm, kam nav kodolieroču, kas ir līgumslēdzējas puses un kas kļūst par Kopienas dalībvalstīm:i) attiecīgajai valstij paziņojot aģentūrai, ka tās procedūras, kas attiecas uz šā līguma stāšanos spēkā, ir izpildītas; unii) Kopienai paziņojot aģentūrai, ka tā ir gatava piemērot savas garantijas, kas attiecas uz šo valsti šā līguma nozīmē.b) Ja attiecīgā valsts ir noslēgusi citus līgumus ar aģentūru par aģentūras garantiju piemērošanu, tad, attiecībā uz šo valsti stājoties spēkā šim līgumam, aģentūras garantiju piemērošanu saskaņā ar šādiem līgumiem pārtrauc uz šā līguma spēkā esamības laiku; tomēr saskaņā ar minētajiem līgumiem turpina piemērot šīs valsts saistības neizmantot elementus, uz ko šie līgumi attiecas tā, ka turpinās šo elementu izmantošana kādam militāram nolūkam.LĪGUMA GROZĪŠANA24.pantsa) Aģentūra, Kopiena un valstis, ja kāda no tām to pieprasa, apspriež šā līguma grozīšanu.b) Visiem grozījumiem vajadzīga aģentūras, Kopienas un valstu vienošanās.c) Ģenerāldirektors nekavējoties informē visas aģentūras dalībvalstis par jebkuru šā līguma grozījumu.STĀŠANĀS SPĒKĀ UN TERMIŅŠ25.pantsa) Šis līgums stājas spēkā dienā, kad aģentūra no Kopienas un valstīm saņem rakstisku paziņojumu par to, ka to prasības, lai līgums stātos spēkā, ir izpildītas.
\nGenerāldirektors nekavējoties informē visas aģentūras dalībvalstis par šā līguma stāšanos spēkā.b) Šis līgums paliek spēkā, kamēr valstis ir līgumslēdzējas puses.PROTOKOLS26.pantsProtokols, kas pievienots šim līgumam, ir tā neatņemama sastāvdaļa. Termins \"līgums\" šajā dokumentā ir līgums kopā ar protokolu.II DAĻAIEVADS27.pantsŠīs līguma daļas mērķis ir pēc vajadzības noteikt procedūras, kas jāpiemēro, realizējot I daļas garantiju noteikumus.GARANTIJU MĒRĶIS28.pantsŠajā līgumā noteikto garantiju procedūru mērķis ir laikus atklāt ievērojamu kodolmateriāla daudzumu novirzīšanu no mierīgām kodoldarbībām kodolieroču vai citu kodolsprādzienierīču ražošanai vai nezināmiem nolūkiem un atturēt no šādas novirzīšanas ar to, ka pastāv ātras atklāšanas iespējamība.29.pantsLai sasniegtu 28.pantā noteikto mērķi, par būtiskas nozīmes garantiju pasākumu izmanto materiāla uzskaiti, kuras nozīmīgi papildu pasākumi ir norobežošana un uzraudzība.30.pantsAģentūras pārbaudes darbību tehniskais noslēgums ir paziņojums par noteiktā periodā nereģistrētā materiāla daudzumu katrā materiālu bilances zonā un paziņoto daudzumu pareizības robežām.KOPIENAS GARANTIJU SISTĒMA31.pantsIevērojot 3.pantu, aģentūra, veicot pārbaudes darbības, pilnīgi izmanto Kopienas garantiju sistēmu.32.pantsKopienas kodolmateriāla uzskaites un kontroles sistēma saskaņā ar šo līgumu pamatojas uz materiālu bilances zonu struktūru.
\nKopiena, piemērojot savas garantijas, izmanto un, ciktāl vajadzīgs, paredz tādus lietderīgus un papildu vienošanās noteiktus pasākumus kā:a) mērīšanas sistēmu, saņemtā, saražotā, nosūtītā, zudušā vai citādi no uzskaites noņemtā kodolmateriāla daudzumu un uzskaitē esošā kodolmateriāla daudzumu noteikšanai;b) mērījumu pareizības un precizitātes novērtēšanu un mērījumu neprecizitātes novērtēšanu;c) procedūras starpību konstatēšanai, pārskatīšanai un novērtēšanai nosūtītāju/saņēmēju mērījumos;d) procedūras fiziskā kodolmateriāla daudzuma uzskaitei;e) procedūras nemērītu daudzumu un nemērītu zudumu uzkrājumu novērtēšanai;f) uzskaites un ziņojumu sistēmu, kas katrā materiālu bilances zonā rāda kodolmateriāla daudzumu un izmaiņas šajā daudzumā, to skaitā saņemto kodolmateriālu un kodolmateriāla nodošanu no materiālu bilances zonas;g) noteikumus, ar ko nodrošina uzskaites procedūru un pasākumu pareizu izpildi; unh) procedūras ziņojumu sniegšanai aģentūrai saskaņā ar 59. - 65. un 67. - 69. pantu.33. pantsGarantijas saskaņā ar šo līgumu nepiemēro materiālam ieguves vai rūdas pārstrādes darbībās.34. pantsa) Ja kādu materiālu, kas satur urānu vai toriju, kurš nav sasniedzis c) punktā aprakstīto kodoldegvielas cikla stadiju, tieši vai netieši eksportē uz valsti, kam nav kodolieroču un kas nav šā līguma puse, Kopiena informē aģentūru par tā daudzumu, sastāvu un galamērķi, ja materiālu neeksportē īpašiem nolūkiem, kuri nav saistīti ar kodoldarbību.b) Ja valstīs importē kādu materiālu, kas satur urānu vai toriju, kurš nav sasniedzis c) punktā aprakstīto kodoldegvielas cikla stadiju, tad Kopiena informē aģentūru par tā daudzumu un sastāvu, ja materiālu neimportē īpašiem nolūkiem, kuri nav saistīti ar kodoldarbību.c) Ja kādu kodolmateriālu, kura sastāvs un tīrība ir piemērota degvielas ražošanai vai bagātināšanai ar izotopiem, izņem no iekārtas vai procesa, kurā tas ražots, vai ja šādu kodolmateriālu vai kādu citu kodolmateriālu, kas ražots vēlākā kodoldegvielas cikla stadijā, importē valstīs, tad uz šo kodolmateriālu attiecas pārējās garantiju procedūras, kuras noteiktas šajā līgumā.GARANTIJU IZBEIGŠANA35.pantsa) Garantijas attiecībā uz kodolmateriālu saskaņā ar šo līgumu beidzas ar nosacījumiem, kas izklāstīti 11.pantā.
\nJa minētā panta nosacījumi nav izpildīti, bet Kopiena uzskata, ka kodolmateriāla atgūšana, uz ko attiecas garantijas saskaņā ar šo līgumu, no atliekām pašlaik nav realizējama vai vēlama, tad aģentūra un Kopiena apspriež attiecīgo garantiju pasākumu piemērošanu.b) Garantijas, kas saskaņā ar šo līgumu attiecas uz kodolmateriālu, beidzas saskaņā ar 13.panta nosacījumiem, ja aģentūra un Kopiena vienojas par to, ka šāds kodolmateriāls ir faktiski neatgūstams.ATBRĪVOJUMI NO GARANTIJĀM36.pantsPēc Kopienas pieprasījuma aģentūra kodolmateriālu no garantijām, kas uz to attiecas saskaņā ar šo līgumu, atbrīvo:a) īpašo skaldmateriālu, ja to lieto gramu vai mazākos daudzumos par devēja elementu instrumentos;b) kodolmateriālu, ja to lieto ar kodolenerģiju nesaistītās darbībās saskaņā ar 13. pantu un šāds kodolmateriāls ir atgūstams; unc) plutoniju, ja plutonija-238 izotopu koncentrācija pārsniedz 80 %.37.pantsPēc Kopienas pieprasījuma aģentūra atbrīvo no garantijām, kas saskaņā ar šo līgumu attiecas uz kodolmateriālu, uz kuru citādi šīs garantijas attiektos, ar noteikumu, ka kopējais kodolmateriāla daudzums, ko saskaņā ar šo pantu atbrīvo no garantijām valstīs, nekad nedrīkst pārsniegt:a) pavisam vienu kilogramu īpašā skaldmateriāla, kas var sastāvēt no vienas šādas sastāvdaļas vai vairākām šādām sastāvdaļām:i) plutonija;ii) urāna, kura bagātinājums ir 0,2 (20 %) vai lielāks, tā masu reizinot ar bagātinājumu; uniii) urāna, kura bagātinājums ir 0,2 (20 %) vai mazāks un pārsniedz dabīgā urāna izotopu saturu, tā masu reizinot ar pieckārtīgu bagātinājuma kvadrātu;b) pavisam 10 tonnām dabīgā urāna un noplicinātā urāna, kura bagātinājums pārsniedz 0,005 (0,5 %);c) 20 tonnām noplicinātā urāna, kura bagātinājums ir 0,005 (0,5 %) vai mazāks; und) 20 tonnām torija;vai tādiem lielākiem daudzumiem, kādus valde var noteikt vienotai piemērošanai.38.pantsJa atbrīvots kodolmateriāls jāpārstrādā vai jāglabā kopā ar kodolmateriālu, uz ko attiecas garantijas saskaņā ar šo līgumu, tad jāparedz šādu garantiju atkārtota piemērošana tam.PAPILDU VIENOŠANĀS39.pantsKopiena papildus vienojas ar aģentūru, tik sīki nosakot, kā jāpiemēro šajā līgumā noteiktās procedūras, cik tas vajadzīgs, lai aģentūra var efektīvi un profesionāli izpildīt savus pienākumus saskaņā ar šo līgumu.
\nPapildu vienošanās var paplašināt vai mainīt, aģentūrai un Kopienai vienojoties, bez grozījumiem šajā līgumā.40.pantsPapildu vienošanās stājas spēkā vienlaikus ar šā līguma stāšanos spēkā vai iespējami drīz pēc tā stāšanās spēkā. Aģentūra, Kopiena un valstis dara visu iespējamo, lai panāktu to stāšanos spēkā 90 dienās pēc šā līguma stāšanās spēkā; par šā perioda pagarināšanu aģentūrai, Kopienai un valstīm jāvienojas. Kopiena nekavējoties sniedz aģentūrai informāciju, kas vajadzīga, lai izpildītu papildu vienošanās. Šim līgumam stājoties spēkā, aģentūrai ir tiesības piemērot tajā noteiktās procedūras, kas attiecas uz kodolmateriālu, kurš uzskaitīts, kā paredzēts 41.pantā, pat tad, ja papildu vienošanās vēl nav stājušās spēkā.UZSKAITE41.pantsPamatojoties uz sākuma ziņojumu, kas minēts 62.pantā, aģentūra valstīs ievieš vienotu visa tā kodolmateriāla uzskaiti, uz kuru attiecas garantijas saskaņā ar šo līgumu, neatkarīgi no tā izcelsmes un turpina šo uzskaiti, pamatojoties uz turpmākajiem ziņojumiem un savu pārbaudes darbību rezultātiem.
\nUzskaites eksemplārus dara pieejamus Kopienai ar intervāliem, par kuriem jāvienojas.PROJEKTA INFORMĀCIJAVispārīgi noteikumi42.pantsIevērojot 8.pantu, projekta informāciju, kas attiecas uz esošajām iekārtām, Kopiena aģentūrai sniedz, apspriežot papildu vienošanās. Termiņus projekta informācijas sniegšanai par jaunām iekārtām nosaka papildu vienošanās un šādu informāciju sniedz iespējami drīz līdz kodolmateriāla ievadīšanai jaunajā iekārtā.43.pantsProjekta informācijā, kas jāsniedz aģentūrai, par katru iekārtu pēc vajadzības jāiekļauj:a) iekārtas identifikācija, norādot tās vispārīgo raksturu, nolūku, nominālo jaudu un ģeogrāfisko atrašanās vietu, kā arī nosaukumu un adresi, kuru var izmantot ikdienas darba nolūkos;b) iekārtas vispārīgā izkārtojuma apraksts, cik pamatoti iespējams, norādot kodolmateriāla formu, atrašanās vietu un plūsmu, kā arī to nozīmīgo iekārtas elementu vispārīgo shēmu, kuros izmanto, ražo vai pārstrādā kodolmateriālu;c) to iekārtas funkciju apraksts, kas attiecas uz materiāla uzskaiti, norobežojumu un uzraudzību; und) iekārtā izmantoto un ierosināto kodolmateriāla uzskaites un kontroles procedūru apraksts ar īpašu norādi uz materiāla bilances zonām, kuras noteicis operators, plūsmas mērīšanas un fiziskā daudzuma noteikšanas procedūru apraksts.44.pantsAģentūrai sniedz arī citu informāciju, kurai ir nozīme garantiju piemērošanai saskaņā ar šo līgumu, attiecībā uz katru iekārtu, ja tā noteikts papildu vienošanās.
\nKopiena sniedz aģentūrai papildu informāciju par veselības aizsardzības un drošības procedūrām, kuras jāievēro aģentūrai un tās inspektoriem iekārtā.45.pantsKopiena sniedz aģentūrai projekta informāciju, kas attiecas uz modifikāciju, kurai ir nozīme attiecībā uz garantijām saskaņā ar šo līgumu, izskatīšanai, un Kopiena laikus informē aģentūru par jebkurām izmaiņām informācijā, ko tā sniegusi aģentūrai saskaņā ar 44. pantu, lai vajadzības gadījumā var pielāgot garantiju procedūras, kuras jāpiemēro saskaņā ar šo līgumu.46.pantsProjekta informācijas izskatīšanas nolūksAģentūrai sniegto projekta informāciju izmanto šādiem nolūkiem:a) lai tik sīki noteiktu tās iekārtu un kodolmateriāla funkcijas, kas ir nozīmīgas garantiju piemērošanai kodolmateriālam, ka pietiekami atvieglo pārbaudi;b) lai noteiktu materiālu bilances zonas, kas jāizmanto uzskaites nolūkiem saskaņā ar šo līgumu, un lai noteiktu stratēģiskos punktus, kuri ir kritiskie mērījumu punkti un kuri jāizmanto kodolmateriāla plūsmas un daudzuma noteikšanai; nosakot šādas materiālu bilances zonas, cita starpā izmanto šādus kritērijus:i) materiālu bilances zonas lielumu attiecina pret pareizību, ar kādu materiālu bilanci var noteikt;ii) nosakot materiālu bilances zonu, izmanto iespēju ar norobežojuma un uzraudzības palīdzību nodrošināt plūsmas mērījumu pilnīgumu, tādējādi vienkāršojot garantiju pie mērošanu un koncentrējot mērīšanu kritiskajos mērījumu punktos;iii) pēc Kopienas vai attiecīgās valsts pieprasījuma var izveidot īpašu materiālu bilances zonu ap procesa stadiju, kas saistīta ar komerciāli konfidenciālu informāciju;c) lai noteiktu nominālos termiņus un procedūras kodolmateriāla fiziskā daudzuma noteikšanai uzskaites nolūkos saskaņā ar šo līgumu;d) lai noteiktu dokumentācijas un ziņojumu prasības un dokumentācijas novērtēšanas procedūras;e) lai noteiktu prasības un procedūras kodolmateriāla daudzuma un atrašanās vietas pārbaudei; unf) lai izraudzītos piemērotas norobežošanas un uzraudzības metožu un paņēmienu kombinācijas un stratēģiskos punktus to piemērošanai.Projekta informācijas izskatīšanas rezultātus pēc aģentūras un Kopienas vienošanās iekļauj papildu vienošanās.47.pantsProjekta informācijas atkārtota izskatīšanaProjekta informāciju atkārtoti izskata saskaņā ar izmaiņām darbības apstākļos, garantiju pasākumu tehnoloģijas attīstību vai pieredzi pārbaudes procedūru piemērošanā, lai modificētu darbību, ko veic, ievērojot 46. pantu.48.pantsProjekta informācijas pārbaudeAģentūra sadarbībā ar Kopienu un attiecīgo valsti var nosūtīt inspektorus uz iekārtām, lai pārbaudītu projekta informāciju, kas 46.pantā noteiktajos nolūkos aģentūrai sniegta, ievērojot 42. - 45.pantu.INFORMĀCIJA, KAS ATTIECAS UZ KODOLMATERIĀLU ĀRPUS IEKĀRTĀM49.pantsJa kodolmateriāks parasti jālieto ārpus iekārtām, tad Kopiena pēc vajadzības sniedz aģentūrai šādu informāciju:a) kodolmateriāla izmantošanas vispārīgu aprakstu, tā atrašanās vietu un lietotāja nosaukumu un adresi ikdienas darba nolūkos; unb) izmantoto un ierosināto kodolmateriāla uzskaites un kontroles procedūru vispārīgu aprakstu, kas noteikts papildu vienošanās.Kopiena laikus informē aģentūru par jebkuru izmaiņu informācijā, kura sniegta saskaņā ar šo pantu.50.pantsInformāciju, kas aģentūrai sniegta, ievērojot 49.pantu, drīkst, ciktāl vajadzīgs, izmantot 46. panta b) - f) punktā noteiktajos nolūkos.DOKUMENTĀCIJAS SISTĒMAVispārīgi noteikumi51.pantsKopiena vienojas par dokumentāciju, kas jākārto attiecībā uz katru materiālu bilances zonu.
\nKārtojamo dokumentāciju apraksta papildu vienošanās.52.pantsKopiena veic pasākumus, lai aģentūras inspektoriem atvieglotu dokumentācijas izskatīšanu, īpaši, ja dokumentācija nav kārtota angļu, franču, krievu vai spāņu valodā.53.pantsŠo dokumentāciju glabā vismaz piecus gadus.54.pantsDokumentācija pēc vajadzības sastāv no:a) tā kodolmateriāla uzskaites dokumentiem, uz kuru attiecas garantijas saskaņā ar šo līgumu; unb) ekspluatācijas dokumentiem, kas attiecas uz iekārtām, kurās ir šāds kodolmateriāls.55.pantsMērījumu sistēma, uz ko pamatojas dokumentācija, kuru izmanto ziņojumu sagatavošanai, atbilst jaunākajiem starptautiskajiem standartiem vai pēc kvalitātes ir līdzvērtīga šādiem standartiem.Uzskaites dokumenti56.pantsUzskaites dokumentos par katru materiālu bilances zonu uzrāda:a) visas kodolmateriālu daudzuma izmaiņas, lai jebkurā laikā var noteikt reģistrēto kodolmateriālu daudzumu;b) visus mērījumu rezultātus, ko izmanto, lai noteiktu fizisko kodolmateriālu daudzumu; unc) visus pielāgojumus un korekcijas, kas izdarītas atkarībā no kodolmateriālu daudzumu izmaiņām, reģistrētajiem kodolmateriālu daudzumiem un fiziskajiem kodolmateriālu daudzumiem.57.pantsDokumentos visas daudzumu izmaiņas un fiziskos daudzumus norāda attiecībā uz katru kodolmateriāla partiju, identificējot materiālu, partijas datus un empīriskos datus. Šajos uzskaites datos atsevišķi norāda urāna, torija un plutonija daudzumu katrā kodolmateriāla partijā.