Key Benefits:
President of the Republic,
On the report of the Prime Minister and the Minister of State, Minister for Foreign and European Affairs,
Considering the Constitution, in particular articles 52 to 55;
Vu la Act No. 2009-1492 of 4 December 2009 authorizing the approval of the cooperation agreement between the Government of the French Republic and the Government of the Republic of India for the development of the peaceful uses of nuclear energy (two annexes), signed in Paris on 30 September 2008;
Vu le Decree No. 53-192 of 14 March 1953 amended on the ratification and publication of international commitments undertaken by France,
Decrete:
The cooperation agreement between the Government of the French Republic and the Government of the Republic of India for the development of the peaceful uses of nuclear energy (two annexes), signed in Paris on 30 September 2008, will be published in the Official Journal of the French Republic.
The Prime Minister and the Minister of State, Minister of Foreign and European Affairs, are responsible, each with regard to him, for the execution of this decree, which will be published in the Official Journal of the French Republic.
A C C O R D
OF COOPERATION IN THE GOVERNMENT OF THE FRENCH REPUBLIC AND GOVERNMENT OF THE REPUBLIC OF INDIA FOR THE DEVELOPMENT OF THE PACIFIC USES OF NUCLEAR ENERGY
The Government of the French Republic and the Government of the Republic of India, referred to as the Parties,
CONSTATING the deep ties of friendship and cooperation between the French Republic and the Republic of India, and the strategic partnership between them in January 1998;
Further observing the existence of an ancient cooperation between the Parties in the field of the use of nuclear energy for peaceful purposes;
RECOGNIZING that nuclear energy is a safe, environmentally friendly and sustainable source of energy, as well as the need to deepen international cooperation to promote the use of nuclear energy for peaceful purposes;
RECOGNIZING that nuclear energy will be an indispensable source of energy for future generations;
RECALLING the existing dialogue on civil nuclear cooperation and nuclear security, and the projects currently being implemented in this dialogue;
RECOGNIZING that both Parties are States with comprehensive capabilities in advanced nuclear technologies, including the nuclear fuel cycle;
DETERMINED that the development of international cooperation for the promotion of the use of nuclear energy for peaceful purposes continues for the mutual benefit of both Parties;
REQUESTS to continue their bilateral cooperation to broaden and deepen civil nuclear cooperation for the development and use of nuclear energy for peaceful purposes, from a sustainable development perspective and to strengthen energy security on a reliable, stable and predictable basis;
WHEREAS, in the interest of the two States, to develop this cooperation in mutual respect for their sovereignty, non-interference in the internal affairs of the other State, equality, mutual benefit, reciprocity, as well as in respect of their respective nuclear programme and in accordance with the principles governing their respective nuclear policies and their respective international obligations;
RECALLING the joint statement by the President of the French Republic and the Prime Minister of the Republic of India of 12 September 2005, and the statement by France and India on the development of nuclear energy for peaceful purposes signed in New Delhi on 20 February 2006, in which the two Parties called for the conclusion between the two countries of a bilateral nuclear cooperation agreement;
Acknowledging that the two States share common concerns and objectives in the field of the non-proliferation of weapons of mass destruction and their means of delivery, including possible links with terrorism, and noting that international cooperation in the field of the peaceful use of nuclear energy must be consistent with these objectives,
AGAINST WHO ITS:
Article I
1. The Parties shall cooperate in the field of the use of nuclear energy for peaceful and non-explosive purposes in accordance with the provisions of this Agreement, in accordance with the principles of international law, in good faith and in accordance with the principles governing their respective nuclear policies and their respective international obligations.
2. The cooperation referred to in the first paragraph of this article may cover the following areas:
– fundamental and applied research does not require the supply of uranium enriched to 20% or more in isotope 235;
development and use of nuclear energy applications in the fields of agronomy, biology, earth sciences and medicine, and in industry;
- full and complete civil nuclear cooperation in nuclear reactors, the provision of nuclear fuel and other agreed aspects between Parties;
- the management of nuclear fuel and the nuclear fuel cycle, including the development of a strategic nuclear fuel reserve to protect itself from any interruption of supply during the life of the guaranteed nuclear reactors in India;
- nuclear waste management;
nuclear safety, radiation protection and environmental protection;
prevention and response to emergency situations resulting from radiological or nuclear accidents;
― controlled thermonuclear fusion, especially in multilateral projects such as ITER;
― public awareness of its acceptance of the benefits of the use of nuclear energy for peaceful and non-explosive purposes,
and any other agreed area between the Parties.
3. Cooperation under this Agreement may take the following forms:
- transfer of industrial or commercial technologies between Parties and persons designated by them;
- exchange and training of scientific and technical staff;
- exchange of scientific and technical information;
- participation of scientific and technical staff from one Party in research and development activities conducted by the other Party;
- joint conduct of research and engineering activities, including joint research and experimentation, i.e. equivalent contributions;
- organization of scientific and technical conferences and seminars;
- provision of nuclear materials, materials, equipment, technologies and facilities, and provision of services, including the development of nuclear-based electricity production projects;
― progressive location in the territory of the Recipient Party, by persons designated by the Parties, through the provision of equipment and components, including by transfer of technology for the implementation of nuclear projects;
- consultations and cooperation within the relevant international forums;
- nuclear cooperation projects in third countries,
and any other form of cooperation agreed by mutual agreement between the Parties.
4. The Parties state that the objective of this Agreement is to implement peaceful nuclear cooperation, not to undermine the nuclear activities of one or the other Party that are not subject to safeguards. Accordingly, no provision of this Agreement shall be construed as impairing the rights of the Parties to use nuclear material, materials, equipment, components, information or technologies produced, acquired or developed by them independently of nuclear material, materials, equipment, components, information or technologies transferred to them in accordance with this Agreement. This Agreement shall be implemented in such a way as not to interfere with or affect any other activity involving the use of nuclear material, materials, equipment, components, information or technology and nuclear facilities not subject to the safeguards, products, acquired or developed by them independently of this Agreement for their own purposes.
Article II
1. Cooperation between the Parties defined in Article I shall be implemented in accordance with the provisions of this Agreement:
- by specific agreements between Parties or persons responsible for the implementation of this Agreement, including scientific and technical programmes and the modalities of scientific and technical exchanges;
- by memorandums of understanding or contracts concluded by persons designated by the Parties concerning industrial achievements and the provision of materials, nuclear materials, services, equipment, installation, location issues and technology transfer, as appropriate.
2. Specific agreements, memorandums of understanding and contracts already concluded between persons designated by the Parties shall be governed by the provisions of this Agreement on the date of its entry into force.
3. The transfer of nuclear material, materials, equipment, components and technologies under this Agreement may be carried out directly between or through the persons designated by them. The nuclear material, materials, equipment, components and technologies transferred from the territory of one Party to the territory of the other Party, directly or via a third country, shall be considered to have been transferred in accordance with this Agreement only after confirmation by the competent authority of the Recipient Party to the competent authority of the Supplier Party that such nuclear material, equipment, components and technologies are both subject to this Agreement and have been received.
Article III
In accordance with their respective national legislation, the Parties shall take all administrative, tax and customs measures of their competence necessary for the effective implementation of this Agreement.
Article IV
1. Both Parties shall cooperate in the design, construction and commissioning of nuclear power plants in accordance with appropriate regulatory requirements.
2. Parties encourage their operators to establish mutually acceptable cooperation in this area.
Article V
1. The Party providing the nuclear power plant facilitates the reliable, uninterrupted and continuous access of the Party to the territory of which the nuclear power plant is located, to nuclear fuel supplies, systems and reactor components during the life of the nuclear power plant provided. With respect to the provision of nuclear fuel for the life of the guaranteed reactors in India, long-term contracts will be passed between the respective designated entities of the Parties in accordance with Article II 1.
2. In order to continue to protect against any interruption of supply during the lifetime of the guaranteed India reactors, France will support Indian efforts to establish a strategic nuclear fuel reserve. This assistance includes the creation by France of a group of friends countries or the accession to such a group created by others in order to implement the measures to restore India's fuel supply in the event of an interruption of this supply.
3. Reprocessing and any other changes in the form or content of nuclear material transferred in accordance with this Agreement, and nuclear material used or produced through the use of nuclear material, nuclear material, equipment or technologies transferred to the Agreement, shall be carried out in a national nuclear facility subject to IAEA safeguards. Any special fissile material so separate may be stored and used in national facilities in the recipient country subject to IAEA safeguards.
Article VI
1. Parties shall facilitate nuclear trade between them in the mutual interest of their respective industries, public services and consumers and, where appropriate, trade between third countries and any of the Parties of articles subject to an obligation to the other Party.
2. The Parties recognize that supply reliability is essential and that it is necessary for the industries of both Parties to be assured at all times that deliveries can be made in time and time, including where appropriate, by progressively locating and ensuring on-site production, in order to effectively plan the operation of nuclear facilities.
Article VII
1. Parties or persons responsible for the implementation of this Agreement shall adequately and effectively protect the intellectual property created and the technology transferred in the framework of cooperation conducted in accordance with this Agreement and the specific agreements, memorandums of understanding and contracts referred to in Article II.
2. Parties shall endeavour to find an agreement on intellectual property rights in order to provide the necessary framework for the implementation of the provisions of this Article.
3. This Agreement does not affect the right to use the intellectual property rights acquired by persons prior to this Agreement. The terms and conditions for the use, attribution and transfer of intellectual property rights are specified on a case-by-case basis in the specific agreements and contracts referred to in Article II of this Agreement.
Article VIII
1. Parties or persons responsible for the implementation of this Agreement shall deal in specific agreements matters relating to liability, including nuclear civil liability.
2. The Parties agree that for the purpose of compensation for damage caused by a nuclear incident involving nuclear materials, equipment, facilities and technologies referred to in Article IX, each Party shall establish a nuclear civil liability regime based on established international principles.
Article IX
The Parties shall ensure that the materials, nuclear materials, equipment, facilities and technologies transferred under this Agreement and the nuclear materials recovered or obtained as by-products are used for peaceful and non-explosive purposes.
Article X
1. In the light of the provisions of Article V, all nuclear materials, equipment, installations and technologies, transferred to the Republic of India under this Agreement and notified by the supplier Party for this purpose, as well as all successive generations of nuclear material recovered or obtained as by-products, shall be subject to the guarantees of the A.I.E.A., under the agreements already entered into by the Republic of India and
2. All nuclear material transferred to the French Republic under this Agreement and notified by the supplier Party for this purpose, as well as all successive generations of nuclear material recovered or obtained as by-products from these transferred nuclear materials, shall be subject to the guarantees of the A.I.E.A., pursuant to the agreement between France, the European Community of Atomic Energy (EURATOM) and the A.I.
3. If the A.I.E.A. decides that the application of safeguards is not possible, the supplier country and the recipient country consult and agree on appropriate verification measures.
Article XI
The substances, nuclear materials, equipment, facilities and technologies referred to in Article IX of this Agreement and the nuclear material recovered or obtained as by-products shall remain subject to the provisions of this Agreement until:
(a) they have been transferred or re-transfered outside the jurisdiction of the receiving Party in accordance with the provisions of Article XV of this Agreement, or have been returned to the Party having initially transferred them, or
(b) Parties agree that they are no longer subject to and subtract from this Agreement, or
(c) in respect of nuclear material, it is established by the A.I.E.A., in accordance with the provisions relating to the lifting of the safeguards contained in the agreements between the Government of the French Republic, EURATOM and A.I.E.A., or between the Government of the Republic of India and A.I.E.A., that they have been consumed or disposed of in such a way that they are usable
Article XII
The Parties shall guarantee security and preserve the confidential nature of the technical data and information designated as confidential by the Party which has provided them under this Agreement. Technical data and information exchanged shall not be communicated to third parties, public or private, without prior written consent by the Party providing technical data or information.
Article XIII
Each Party shall ensure that the nuclear materials, nuclear materials, equipment, facilities and technologies referred to in Article IX of this Agreement and the nuclear materials recovered or obtained as by-products are only held by persons under its jurisdiction and authorized by it to do so.
Article XIV
1. Each Party shall ensure that, in its territory, or outside its territory, to the extent that such liability is assumed by the other Party or by a third State, the appropriate physical protection measures are taken in respect of the nuclear materials, materials, equipment and facilities referred to in this Agreement in accordance with its national legislation and the international commitments to which it is a party, including the Convention on the Physical Protection of Nuclear Material of 26 October 1979 and the amendment to that Convention adopted on 8 July 2005
2. For nuclear materials, physical protection levels are at least those specified in Annex I to the Convention. Each Party reserves the right, where appropriate, in accordance with its national regulations, to apply stricter physical protection criteria.
3. The implementation of physical protection measures is the responsibility of each Party within its jurisdiction. For the implementation of these measures, each Party draws on the recommendations of the A.I.E.A. contained in INFCIRC 225/Rev. 4.
4. The amendments to the A.I.E.A.'s recommendations on physical protection have no effect under this Agreement after the two parties have notified each other in writing of their acceptance of these amendments.
Article XV
In the event that one of the Parties intends to transfer to a third State the nuclear material, materials, equipment, facilities and technologies referred to in Article IX, or to transfer materials, nuclear materials, equipment, facilities and technologies referred to in Article IX from the equipment or facilities transferred to the origin or obtained through the equipment, facilities or technologies transferred, it shall only do so after obtaining from the consignee of these transfers the assurance of an explosive or In addition, it collects prior written consent from the other Party, except in cases where the proposed transfer or retransfer is intended for a Member State of the European Union.
Article XVI
None of the provisions of this Agreement shall be construed as infringing obligations that, at the date of its signature, result from the participation of either Party in other international agreements for the use of nuclear energy for peaceful purposes, including, for the French Party, its membership in the European Communities.
Article XVII
1. The Parties undertake to consult at the request of either of them regarding the implementation of this Agreement and the continued cooperation in the peaceful uses of nuclear energy on a stable, reliable and predictable basis. The Parties recognize that this cooperation is carried out between two States that possess advanced nuclear technologies and, while ensuring that the Parties withdraw the same benefits and benefits, consult in the manner and in the manner specified in paragraph 2 of this Article in order to achieve the full and complete cooperation provided for in Articles I and II and to effectively implement this Agreement. These consultations are formalized through a joint committee established for this purpose.
2. Representatives of the Parties shall meet at the request of one of the Parties to consult on matters arising from the application of this Agreement.
3. Each Party shall endeavour to avoid any action that affects the cooperation specified in Article I of this Agreement. If one of the Parties decides, at any time after the entry into force of this Agreement, that the other Party shall not comply with any of the provisions of this Agreement, the Parties shall consult promptly to resolve the matter in order to protect the legitimate interests of the two Parties, provided that the rights of each Party under paragraph 6 of Article XX are not affected.
4. Dispute settlement procedures resulting from contractual obligations related to the implementation of this Agreement are specified in the relevant commercial contracts between the persons designated by each Party.
Article XVIII
1. The two Parties agree that the terms and provisions contained in this Agreement shall not be amended during the period of validity of this Agreement unless the two Parties, by mutual consent and in written agreement between the Parties, decide otherwise.
2. Any amendment to this Agreement shall be subject to ratification, acceptance or approval by the Parties in accordance with their respective constitutional provisions. Each Party shall notify the other of the fulfilment of these procedures. The amendments come into force on the date of receipt of the last notification.
Rule XIX
The annexes to this Agreement shall be an integral part of this Agreement.
Rule XX
1. Each Party shall notify the other Party of the completion of the required procedures for the entry into force of this Agreement.
2. This Agreement shall take effect on the date of receipt of the last notification.
3. This Agreement shall be concluded for a period of forty (40) years. It is renewable by tacit renewal for periods of twenty (20) years. A Party that does not wish to renew this Agreement shall notify the other Party in writing with a notice of six months.
4. Each party has the right to denounce this Agreement before its expiry by giving written notice of one year to the other Party. The Party giving notice of denunciation shall provide the reasons for this denunciation. Both Parties consider it very unlikely that one of the Parties will commit acts that incite the other Party to denounce this Agreement. If the Party wishing to denounce it cites a violation of the Agreement as a ground for its notice of denunciation, the Parties shall determine whether that act has been committed inadvertently or otherwise and whether that violation may be considered substantial.
5. The Agreement shall expire one year after the date of written notice, unless the Party that had sent it has withdrawn it in writing before the expiry date. The end of cooperation does not affect the implementation of existing contracts, projects and fuel supply commitments under this Agreement before the end of cooperation.
6. In case of non-reconduction of this Agreement in accordance with the procedure referred to in paragraph 3 of this article or denunciation in accordance with the procedure referred to in paragraph 4 of this article:
- the relevant provisions of this Agreement shall remain applicable to specific agreements and contracts signed under Article II, which are in force;
— the provisions of Articles VII, VIII, IX, X, XI, XII, XIII, XIV, XV and XVI shall continue to apply, where appropriate, to nuclear material, equipment, facilities and technologies referred to in Article IX and transferred under this Agreement, as well as to nuclear material recovered or obtained as by-products, and shall remain in force.
IN WITNESS WHEREOF, the representatives of the two Governments duly authorized to do so have signed this Agreement.
Done in Paris on 30 September 2008, in two copies, in French, English and Hindi, the three texts being equally authentic.
For the Government
of the French Republic:
Bernard Kouchner
Minister of Affairs
Foreign and European
For the Government
of the Republic of India:
Doctor Anil Kakodkar
Secretary-General, Department
of Atomic Energy
A N N E X E 1
This Annex is an integral part of the Agreement.
For the purposes of this Agreement:
(a) "person" means any natural person or legal person subject to the territorial jurisdiction of either Party, excluding the Parties themselves;
(b) "material" means non-nuclear substances for reactors, as specified in paragraph 2 of Annex 2 to this Agreement, being an integral part of this Agreement;
(c) "nuclear matter" means any "gross material" or "special fissile material", as defined in Article XX of the Statute of the A.I.E.A.;
(d) "Nuclear material recovered or obtained as a by-product" means nuclear material obtained from nuclear material transferred under this Agreement, or through one or more treatments using equipment or facilities transferred under this Agreement or using equipment or facilities based on technology transferred under this Agreement;
(e) "equipment" means the main components specified in paragraphs 1, 3 to 7 of Appendix 2;
(f) "installations" means the plants referred to in paragraphs 1, 3 to 7 of Schedule 2;
(g) "technology" means the specific information required for "development", "production" or "use" of items referred to in Appendix 2, with the exception of "public" or "basic scientific research" data.
"Development" refers to all phases prior to "production", such as studies, design research, functional analysis, pre-project concepts, the assembly and testing of prototypes, production pilot projects, the definition of technical data, the process of conversion of technical data to product, the design of configuration, the design of integration, the implementation plans.
"Production" means all phases of production such as construction, production engineering, manufacturing, integration, assembly (mounting), inspection, testing, quality assurance.
By "use", It is appropriate to hear implementation, installation (including installation on the site itself), maintenance, repairs, revision dismantling and rehabilitation.
"Basic scientific research" means experimental or theoretical work undertaken primarily to acquire new knowledge on the fundamental principles of phenomena and observable facts and not essentially a specific purpose or practical objective.
The term "in the public domain" refers here to the fact that technology has been made available without restrictions on broader dissemination (restrictions resulting from copyright do not prevent technology from being in the public domain).
(h) The term "information" means any information that is not in the public domain, transferred in any form under this Agreement, archived in printed or digital form, and designated by agreement between the Parties under this Agreement, but ceases to be information when the Party transferring information or any third party legitimately distributes it in the public domain.
(i) "Intellectual property" has the meaning of Article 2 of the Convention establishing the World Intellectual Property Organization (WIPO), signed in Stockholm on 14 July 1967.
A N N E X E 2
This Annex is an integral part of the Agreement.
1. Nuclear reactors
and equipment for these reactors
1.1. Comprehensive nuclear reactors
Nuclear reactors that can operate in such a way as to maintain a controlled self-sustained chain fission reaction, except for zero power reactors that are defined as reactors whose maximum production of plutonium does not exceed 100 grams per year.
1.2. Nuclear reactor tanks
Metal tanks, or important prefabricated elements of such tanks, which are specially designed or prepared to contain the heart of a nuclear reactor in the sense given to this expression in paragraph 1.1. above, as well as reactor internals in the sense given to this expression in point 1.8 below.
1.3. Machines for loading
and the unloading of nuclear fuel
Handling equipment specially designed or prepared to introduce or extract the fuel from a nuclear reactor in the sense given to this expression in paragraph 1.1 above.
1.4. Control bars for reactors
and related equipment
Dams, support or suspension structures, training mechanisms or guide tubes of control bars, specially designed or prepared to control the fission process in a nuclear reactor in the sense given to this expression in 1.1 above.
1.5. Power tubes for reactors
Tubes specially designed or prepared to contain the fuel elements and the primary cooling fluid of a nuclear reactor in the sense given to this expression in point 1.1 above, at working pressures greater than 50 atmospheres.
1.6. Zirconium tubes
Metal zirconium and zirconium-based alloys, in the form of tubes or assemblies of tubes, supplied in quantities greater than 500 kg for a period of 12 months irrespective of the recipient country, specially designed or prepared to be used in a nuclear reactor in the sense given to this expression in point 1.1 above, and in which the hafnium/zirconium ratio is less than 1/500 parts by weight.
1.7. Primary circuit pumps
Pumps specially designed or prepared to circulate the primary cooling fluid for nuclear reactors in the sense given to this expression in point 1.1 above.
1.8. Nuclear reactor interns
"Nuclear reactor interns" specially designed or prepared for use in a nuclear reactor in the sense given to this expression in point 1.1 above, including core support columns, fuel channels, thermal screens, deflectors, heart grille plates and distribution plates.
1.9. Heat exchangers
Heat exchangers (steam generators) specially designed or prepared for use in the primary cooling circuit of a nuclear reactor in the sense given to this expression in point 1.1 above.
1.10. Neutron detection and measurement instruments
Neutron detection and measurement instruments specially designed or prepared to assess neutron fluxes in the heart of a nuclear reactor in the sense given to this expression in point 1.1 above.
2. Non-nuclear substances for reactors
2.1. Deuterium and heavy water
Deuterium, heavy water (deuterium oxide) and any deuterium compound in which the deuterium/hydrogen atomic ratio exceeds 1/5000, intended to be used in a nuclear reactor, in the sense given to that expression in point 1.1 above, and supplied in quantities exceeding 200 kg of deuterium atoms for a period of 12 months, regardless of the recipient country.
2.2. Nuclear purity graphite
Graphite with a purity greater than five parts per million boron equivalent and a density greater than 1.50 g/cm3, which is intended to be used in a nuclear reactor in the sense given to this expression in point 1.1 above and which is supplied in quantities greater than 30 metric tons for a period of 12 months, irrespective of the recipient country.
3. irradiated fuel reprocessing plants and equipment specially designed or prepared for this purpose
3.1. Degainer machines
irradiated fuel elements
Remote-controlled machines specially designed or prepared to be used in a reprocessing plant in the sense given above, and intended to disassemble, cut or wield irradiated nuclear fuel assemblies, beams or rods.
3.2. Dissolvers
Containers "geometrically safe" (small diameter, rings or flats) specially designed or prepared to be used in a reprocessing plant, in the sense given above, to dissolve irradiated nuclear fuel, capable of resisting highly corrosive hot liquids and whose loading and maintenance can be remotely controlled.
3.3. Extractors and solvent extraction equipment
Extractors, such as pulsed or garnished columns, centrifugal mixers and extractors, specially designed or prepared to be used in an irradiated fuel reprocessing plant. The extractors must be able to withstand the corrosive action of nitric acid. The extractors are normally manufactured according to very strict requirements (e.g. special welding, inspection and quality assurance techniques), low-carbon stainless steel, titanium, zirconium or other high-strength materials.
3.4. Solutions collection or storage containers
Collection or storage containers specially designed or prepared for use in an irradiated fuel reprocessing plant. Collection or storage containers must be able to withstand the corrosive action of nitric acid. Collection or storage containers are normally manufactured using materials such as low-carbon stainless steel, titanium or zirconium or other high-strength materials. Collection or storage containers may be designed for remotely controlled conduct and maintenance and may have the following characteristics to prevent criticality risk:
1. Parois or internal structures with a boron equivalent of at least two percent;
2. A maximum diameter of 175 mm (7 inches) for cylindrical receptacles;
3. A maximum width of 75 mm (3 inches) for flat or ring vessels.
4. Fuel element manufacturing plants
Nuclear reactors
"Nuclear reactor fuel manufacturing plant" includes equipment that:
a. Normally they are in direct contact with the flow of nuclear material produced, or directly process or control this flow;
b. seal nuclear material inside the sheath;
c. Check the integrity of the sheath or sealing;
d. Check the finishing treatment of the sealed fuel.
5. Uranium isotope separation plants and equipment, other than analytical devices, specially designed for this purpose
Articles considered to fall into the category covered by the expression " and equipment, other than analytical apparatus, specially designed or prepared" for the separation of uranium isotopes:
5.1. Centrifuges and assemblies and components especially
designed or prepared for use in centrifuges
5.1.1. Rotating components
(a) Complete rotor assemblies.
Thin-wall cylinders, or assembled thin-wall cylinders, manufactured in one or more of the high-density-resistance materials described in the Explanatory Note below; When combined, the cylinders are attached to each other by the flexible bellows or rings described in 5.1.1 (c) below. The bowl is equipped with one or more internal chicanes and end caps, as indicated in points 5.1.1 (d) and (e) below, if ready for use. However, the complete assembly can be delivered partially assembled only;
(b) Bols.
thin-walled cylinders with a thickness of 12 mm (0.5 inches) or less, specially designed or prepared, having a diameter of 75 mm (3 inches) and 400 mm (16 inches) and manufactured in one or more of the high-density-resistance materials described in the Explanatory Note below;
(c) Rings or bells.
Components specially designed or prepared to provide local support to the bowl or to join together several cylinders constituting the bowl. The bellow is a short cylinder with a wall of 3 mm (0.12 inches) or less thickness, a diameter between 75 mm (3 inches) and 400 mm (16 inches) and a spire, and manufactured in one of the materials with a high strength-density ratio described in the Explanatory Note;
(d) Chicanes.
Disk-shaped components of a diameter between 75 mm (3 inches) and 400 mm (16 inches), specially designed or prepared to be mounted inside the bowl of the centrifuge in order to isolate the sampling chamber of the main separation chamber and, in some cases, facilitate the circulation of the UF6 gaseous inside the main separation chamber of the bol, and manufactured in one of the following materials
(e) Upper and lower end caps.
Disk-shaped components of a diameter between 75 mm (3 inches) and 400 mm (16 inches), specially designed or prepared to adapt to the ends of the bowl and thus maintain the UF6 inside the bowl and, in some cases, to carry, retain or contain as an integral part an element of the upper bearing (higher corkscrew) or to carry the rotating elements of the engine and lower bearing (lower corkscrew)
EXPLANATORY NOTE
Materials used for rotating centrifuge components are:
(a) Aging martensitic steels with a breaking limit load equal to or greater than 2.05.109 N/m2 (300,000 psi) or more;
(b) Aluminum alloys with a breaking limit load equal to or greater than 0.46.109 N/m2 (67 000 psi) or more;
(c) filament materials that can be used in composite structures and have a specific module equal to or greater than 3.18.106 m, and a specific burst limit load equal to or greater than 7.62.104 m (the "specific module" is the Young module expressed in N/m2 divided by the density expressed in N/m3; the "specific break limit load" is the break limit load expressed in N/m2 divided by the density expressed in N/m3).
5.1.2. Fixed components
(a) Magnetic suspension lights.
Support assemblies specially designed or prepared including an annular magnet suspended in a pad containing a damper medium. The crankcase is made in a resistant UF6 material (see Explanatory Note in section 5.2). The magnet is coupled to a polar piece or a second magnet attached to the top end cap described in point 5.1.1 (e). The ring magnet may have a ratio between the outer diameter and the inner diameter less than or equal to 1.6:1. The magnet can have an initial permeability equal to or greater than 0.15 H/m (120,000 in CGS units), or an electromagnetic energy density greater than 80 kJ/m3 (107 gauss-œrsteds). In addition to the usual properties of the material, an essential condition is that the deviation of magnetic axes from geometric axes is limited by very tight tolerances (lower than 0.1 mm or 0.004 inches) or that the homogeneity of the magnet material is specially imposed;
(b) Thread/dampers.
Pallets specially designed or prepared including a pivot/cut assembly mounted on a damper. The pivot usually consists of a tempered steel tree with a hemisphere at one end and a fixture device at the lower end described in point 5.1.1 (e) at the other end. However, the tree can be equipped with a hydrodynamic bearing. The cup has the shape of a watermelon with hemispheric indentation on a surface. These components are often supplied independently of the damper;
(c) Molecular pumps.
Cylinders specially designed or prepared that contain helicoidal stripes obtained by machining or extrusion on their inner faces and whose holes are aroused. Their usual dimensions are: internal diameter between 75 mm (3 inches) and 400 mm (16 inches), wall thickness equal to or greater than 10 mm and length equal to or greater than diameter. Usually the stripes have a rectangular section and a depth equal to or greater than 2 mm (0.08 inches);
(d) Engine stators.
Ancillary Stators specially designed or prepared for high-speed hysteresis (or reluctance) engines powered in multiphase AC current for synchronous operation in the vacuum with a frequency range of 600 to 2,000 Hz, and a power range of 50 to 1,000 VA. The stators are made of multiphase windings on soft leafy iron cores consisting of thin layers whose thickness is usually less than or equal to 2 mm (0.08 inches);
(e) Offences of centrifuge.
Components specially designed or prepared to contain the rotor assembly of a centrifuge. The enclosure consists of a rigid cylinder with a wall of not more than 30 mm (1.2 inch) of thickness, having undergone precision machining at the ends to receive bearings and which is equipped with one or more flanges for mounting. The worn ends are parallel to each other and perpendicular to the longitudinal axis of the cylinder with a deviation equal to 0.05 degrees. The enclosure can also be formed of an alveolar type structure allowing to accommodate several bowls. The enclosures are made or coated with corrosion-resistant materials by the U6;
(f) Ecopes.
Tubes with an internal diameter of not more than 12 mm (0.5 inches), specially designed or prepared to extract the UF6 gaseous contained in the bowl according to the Pitot tube principle (i.e., their opening leads into the peripheral gas stream inside the bowl, configuration obtained for example by curving the end of a tube arranged according to the radius) and which can be connected to the central sampling system of the gas. The tubes are made of or coated with corrosion-resistant materials by the U6.
5.2. Systems, equipment and auxiliary components specially designed or prepared for use in ultracentrifugation enrichment plants
5.2.1. Feeding systems/sampling systems
and residues
Systems specially designed or prepared including:
Power autoclaves (or stations) used to introduce UF6 into centrifuge cascades at a pressure of up to 100 kPa (15 psi) and at a flow rate of 1 kg/h;
Cold traps used to remove UF6 from cascades at a pressure of up to 3 kPa (0.5 psi). Cold traps can be cooled up to 203 K (―70 °C) and heated up to 343 K (70 °C);
"Product" and "Residues" stations for the transfer of the U6 into containers.
These equipments and pipes are made entirely or coated internally with UF6-resistant materials (see Explanatory Note to this section) and are manufactured according to very stringent vacuum and cleanliness standards.
5.2.2. Collecteurs/tuyauteries
Tuyauteries and collectors specially designed or prepared for handling the U6 inside the centrifuge cascades. The piping is usually the "three" collector type, each centrifuge being connected to each collector. The repetitiveness of the installation of the system is therefore large. The system is made entirely of UF6-resistant materials (see Explanatory Note of this section) and is manufactured according to very stringent vacuum and cleanliness standards.
5.2.3. Mass spectrometers for UF6/ion sources
Spectrometers of magnetic or quadripolar mass specially designed or prepared, capable of taking live samples of the gas input, product or residue from the UF6 gas streams, and having all the following characteristics:
1. Unitary resolution power for atomic mass unit greater than 320;
2. Sources of nichrome or monel or nickel-plated ions;
3. Ionization sources by electronic bombardment;
4. Presence of a collector adapted to isotopic analysis.
5.2.4. Frequency converters
Frequency converters specially designed or prepared for the supply of motor stators described in 5.1.2(d), or parts, components and sub-assemblies of frequency converters, having all the following characteristics:
1. Multiphase output from 600 to 2,000 Hz;
2. High stability (with frequency control greater than 0.1%);
3. Low harmonic distortion (lower than 2%);
4. Over 80%.
EXPLANATORY NOTE
The items listed above are in direct contact with the UF6 gas, either directly control the centrifuges and the passage of the gas from one centrifuge to another and from one cascade to another.
UF6 corrosion-resistant materials include stainless steel, aluminum, aluminum alloys, nickel and alloys containing 60% or more nickel.
5.3. Assembly and components specially designed or prepared for use in gas enrichment
5.3.1. Gas diffusion barriers
(a) Slender and porous filters specially designed or prepared, which have pores of a diameter of 100 to 1000 angströms, a thickness equal to or less than 5 mm (0.2 inches) and, in the case of tubular shapes, a diameter equal to or less than 25 mm (1 inches) and are made of metallic, polymer or ceramic materials resistant to corrosion by the U6.
(b) Composed or prepared powders specially for the manufacture of these filters. These compounds and powders include nickel and alloys containing 60% or more nickel, aluminum oxide and totally fluorinated hydrocarbon polymers with a purity equal to or greater than 99.9%, a grain size less than 10 microns and a great uniformity of this size, which are specially prepared for the manufacture of gas diffusion barriers.
5.3.2. Diffusers
Enclosures specially designed or prepared, hermetically sealed, of cylindrical shape and having more than 300 mm (12 inches) of diameter and more than 900 mm (35 inches) of long, or rectangular shape with comparable dimensions, which are equipped with an inlet connection and two outlet fittings with all more than 50 mm (2 inches) of diameter, intended to contain the gas diffusion barrier,
5.3.3. Compressors and gas blowers
Axial, centrifugal or volumetric compressors and gas blowers specially designed or prepared, having a suction capacity of 1 m3/min or more UF6 and an output pressure of up to several hundred kPa (100 psi), designed to operate for a long time in the atmosphere of UF6, with or without an appropriate power electric motor, and separate assemblies of compressors and blowers. These gas compressors and blowers have a compression ratio between 2/1 and 6/1 and are made or coated internally with UF6-resistant materials.
5.3.4. Tree seals
Vacuum fittings specially designed or prepared, with power and exhaust connections, to ensure reliable sealing of the shaft connecting the compressor rotor or gas blower to the drive engine by preventing the air from entering the compressor's inner chamber or gas blower that is filled with U6. These fillings are normally designed for a buffer gas penetration rate of less than 1000 cm3/min (60 cubic inches/min).
5.3.5. Heat exchangers
for the cooling of the U6
Heat exchangers specially designed or prepared, made or coated inwardly of U6-resistant materials (with the exception of stainless steel) or copper or a combination of these metals and intended for a pressure variation rate due to leakage that is less than 10 Pa (0,001 5 psi) per hour for a pressure difference of 100 kPa (15 psi).
5.4. Systems, equipment and auxiliary components specially designed or prepared for use in gas enrichment
Introductory note
The systems, equipment and auxiliary components of gas enrichment plants are the systems necessary to introduce the UF6 into the gaseous diffusion assembly, to connect the assemblies to each other in cascades (or floors) in order to obtain increasing enrichment rates, and to take the UF6 into the diffusion cascades as a "product" and "residual" and "residual". Due to the strong inertia properties of diffusion cascades, any interruption in their operation, and in particular their shutdown, has serious consequences. The maintenance of a strict and constant vacuum in all systems of the process, automatic accident protection and precise automatic adjustment of the gas flow are therefore of great importance in a gas diffusion plant. All this forces the plant to be equipped with a large number of special control, control and measurement systems. Usually, the UF6 is sublimated from cylinders placed in autoclaves and sent to the gaseous state at the point of entry thanks to a tubular waterfall collector. The "product" and "residues" flows from the outlet points are routed by a cascade tubular collector to the cold traps or compression stations where the UF6 gas is liquefied before being transferred to appropriate transport or storage containers. Since a gas-spread enrichment plant contains a large number of gas-spread assemblies arranged in cascades, there are several kilometers of pipes with thousands of welds, which presupposes a considerable repetition of the assembly. Equipment, components and pipes are manufactured according to very strict vacuum and cleanliness standards.
5.4.1. Feeding systems/sampling systems
and residues
Systems specially designed or prepared, capable of operating at pressures equal to or less than 300 kPa (45 psi) and comprising:
Power autoclaves (or systems) used to introduce UF6 into gaseous diffusion cascades;
Cold traps used to remove UF6 from diffusion cascades;
Liquefaction stations where the UF6 gas from the cascade is compressed and cooled to obtain liquid UF6;
"Product" or "Residues" stations for the transfer of the U6 into containers.
5.4.2. Collecteurs/tuyauteries
Tuyauteries and collectors specially designed or prepared for handling the UF6 inside the gaseous diffusion cascades. The piping is normally "double" collector type, each cell being connected to each collector.
5.4.3. Vacuum systems
(a) Large vacuum dispensers, vacuum collectors and vacuum pumps with a suction capacity of 5 m3/min (175 cubic feet/min), specially designed or prepared;
(b) Vacuum pumps specially designed to operate in the atmosphere of UF6, made or coated in aluminium, nickel or alloys with more than 60% nickel. These pumps can be rotary or volumetric, be on the move and have fluorocarbon seals and be equipped with special service fluids.
5.4.4. Special stop and adjustment valves
Stop and adjusting blows, manual or automatic, specially designed or prepared, consisting of U6-resistant materials with a diameter of between 40 and 1,500 mm (1.5 to 59 inches) for installation in main and auxiliary systems of gaseous enrichment plants.
5.4.5. Mass spectrometers for UF6/ion sources
Spectrometers of magnetic or quadripolar mass specially designed or prepared, capable of taking live samples of the gas input, product or residue from the UF6 gas streams, and having all the following characteristics:
1. Unitary resolution power for atomic mass unit greater than 320;
2. Sources of nichrome or monel or nickel-plated ions;
3. Ionization sources by electronic bombardment;
4. Collector suitable for isotopic analysis.
5.5. Systems, equipment and components specially designed or prepared for use in aerodynamic process enrichment plants
5.5.1. Separation pipes
Separation pipes and separation pipe assemblies specially designed or prepared. Separation tubers consist of slit-section curved channels, radius of curvature less than 1 mm (usually comprised between 0.1 and 0.05 mm), resistant to corrosion by the UF6, in which a squeezer separates in two fractions the gas circulating in the tile.
5.5.2. wormhole tubes
wormhole tubes and vortex tube assemblies, specially designed or prepared. The vortex tubes, of cylindrical or conical shape, are made of or coated with corrosion-resistant materials by the UF6, have a diameter between 0.5 cm and 4 cm and a length/diameter ratio less than or equal to 20:1, and are equipped with one or more tangential intake channels. Tubes can be equipped with tuyère-type devices at either end or at both ends.
5.5.3. Compressors and gas blowers
Axial compressors, centrifugal or volumetric or gas blowers specially designed or prepared, made or coated with corrosion-resistant materials by the UF6 and with a suction capacity of the mixture of UF6 and carrying gas (hydrogen or helium) of 2 m3/min or more.
5.5.4. Tree seals
Specially designed or prepared fittings, with power and exhaust connections, to ensure reliable sealing of the shaft connecting the compressor rotor or gas blower to the drive engine by preventing the process gas from escaping, or the air or gas leakage to enter the inner chamber of the compressor or gas blower that is filled with the gas blower.
5.5.5. Heat exchangers
for the cooling of the gas mixture
Heat exchangers specially designed or prepared, made or coated with corrosion-resistant materials by the UF6.
5.5.6. Enclosures containing elements of separation
Enclosures specially designed or prepared, made or coated with corrosion-resistant materials by UF6, intended to receive vortex tubes or separation tubers.
5.5.7. Feeding systems/sampling systems
and residues
Systems or equipment specially designed or prepared for enrichment plants, made or coated with corrosion-resistant materials by the UF6 including:
(a) Autoclaves, ovens and feeding systems used to introduce the UF6 into the enrichment process;
(b) Cold traps used to remove 1'UF6 from the enrichment process for its subsequent transfer after warming;
(c) Solidification or liquefaction stations used to remove UF6 from the enrichment process, by compression and transition to liquid or solid state;
(d) "Product" or "Residues" stations for the transfer of the U6 into containers.
5.5.8. Collecteurs/tuyauteries
Tuyauteries and collectors made or coated with corrosion-resistant materials by UF6, specially designed or prepared for handling UF6 inside aerodynamic cascades. The piping is normally "double" collector type, each floor or group of floors being connected to each collector.
5.5.9. Vacuum systems and pumps
(a) Vacuum systems specially designed or prepared, with a suction capacity greater than or equal to 5 m3/min, including vacuum dispensers, vacuum collectors and vacuum pumps designed to operate in the atmosphere of UF6.
(b) Vacuum pumps specially designed or prepared to operate in the atmosphere of UF6, and made or coated with corrosion-resistant materials by UF6. These pumps can be equipped with fluorocarbon seals and special service fluids.
5.5.10. Special stop and adjustment valves
Stop and adjusting blows, manual or automatic, consisting or coated with corrosion-resistant materials by the U6 and having a diameter of 40 to 1,500 mm, specially designed or prepared for installation in main or auxiliary systems of enrichment plants by aerodynamic process.
5.5.11. Mass spectrometers for UF6/ion sources
Spectrometers of magnetic or quadripolar mass specially designed or prepared, capable of taking live samples of the gas input, product or residue from the UF6 gas streams, and having all the following characteristics:
1. Unitary resolution power for atomic mass unit greater than 320;
2. Sources of nichrome or monel or nickel-plated ions;
3. Ionization sources by electronic bombardment;
4. Collector suitable for isotopic analysis.
5.5.12. UF6 separation systems
and carrying gas
Systems specially designed or prepared to separate the UF6 from the carrying gas (hydrogen or helium).
5.6. Systems, equipment and components specially designed or prepared for use in enrichment plants by chemical exchange or ion exchange
5.6.1. Liquid-liquid exchange columns
(chemical exchange)
Liquid-liquid counter-current exchange columns with mechanical power supply (i.e. pulsed columns with perforated trays, columns with an alternative movement and columns with internal turbo agitators), specially designed or prepared for the enrichment of uranium through the chemical exchange process. In order to make them resistant to corrosion by solutions in concentrated hydrochloric acid, the columns and their internals are made or coated with appropriate plastic materials (for example, polymer fluorocarbons) or glass. The columns are designed so that the living time corresponding to one floor is short (30 seconds at most).
5.6.2. Liquid-liquid centrifugal contactors
(chemical exchange)
Liquid-liquid centrifugal contactors specially designed or prepared for uranium enrichment through the chemical exchange process. In these contactors, the dispersion of organic and aqueous fluxes is obtained by rotation, and the separation of phases by application of a centrifugal force. In order to make them resistant to corrosion by solutions in concentrated hydrochloric acid, the contactors are made of or coated with appropriate plastic materials (for example, polymer fluorocarbons) or glass-coated. Centrifugal contactors are designed so that the living time corresponding to one floor is short (30 seconds at most).
5.6.3. Reduction systems and equipment
uranium (chemical exchange)
(a) Electrochemical reduction cells specially designed or prepared to reduce uranium from a state of valence to a lower state for its enrichment through the chemical exchange process. Cell materials in contact with process solutions must be corrosion resistant by solutions in concentrated hydrochloric acid.
(b) Systems at the end of the cascade where the product is recovered, specially designed or prepared to remove U4+ from the organic stream, adjust the acid concentration and feed the electrochemical reduction cells.
5.6.4. Food preparation systems
(chemical exchange)
Systems specially designed or prepared to produce high purity uranium chloride solutions to feed uranium isotope separation plants by chemical exchange.
5.6.5. Uranium oxidation systems
(chemical exchange)
Systems specially designed or prepared to oxidize U3+ in U4+ for reflux to the isotope separation cascade in the chemical exchange enrichment process.
5.6.6. Ion/adsorbent exchangers
rapid reaction (ion exchange)
Rapid reaction ion exchangers or adsorbent resins specially designed or prepared for uranium enrichment through the ion exchange process, in particular macro-linked porous resins and/or film structures in which active chemical exchange groups are limited to a surface coating on an inactive porous medium, and other composite structures in an appropriate form, and in particular in an appropriate form. These items have a diameter of less than or equal to 0.2 mm; from a chemical point of view, they must be resistant to solutions in concentrated hydrochloric acid and, from a physical point of view, be sufficiently solid to not degrade in the exchange columns. They are specially designed to obtain very high exchange rates of uranium isotopes (half-reaction time less than 10 seconds) and are effective at temperatures between 100 °C and 200 °C.
5.6.7. Ion exchange colonies (ion exchange)
Cylindrical columns of more than 1,000 mm in diameter containing an ion/adsorbant exchange resin filling, specially designed or prepared for uranium enrichment through the ion exchange process. These columns are made or coated with materials (such as titanium or fluorocarbon-based plastics) resistant to corrosion by solutions in concentrated hydrochloric acid, and can operate at temperatures between 100 °C and 200 °C and at pressures greater than 0.7 MPa (102 psi).
5.6.8. Reflux systems (ion exchange)
(a) Chemical or electrochemical reduction systems specially designed or prepared to regenerate the chemical reduction agent (agents) used in uranium enrichment cascades through the ion exchange process.
(b) Chemical or electrochemical oxidation systems specially designed or prepared to regenerate the chemical oxidation agent (agents) used in uranium enrichment cascades through the ion exchange process.
5.7. Systems, equipment and components specially designed and prepared for use in laser enrichment plants
5.7.1. Uranium vaporization systems (SILVA)
Uranium vaporization systems specially designed or prepared, containing high-powered electron cannons with table or sweeping beams, providing a target power greater than 2.5 kW/cm.
5.7.2. Handling systems
Uranium Liquid Metal (SILVA)
Liquid metal handling systems specially designed or prepared for uranium or melted uranium alloys, including hollows and cooling equipment for hollows.
5.7.3. Collections of the product
and metal uranium residues (SILVA)
Collections of the product and residues specially designed or prepared for uranium metal in liquid or solid state.
5.7.4. Separator module enclosures (SILVA)
Cylindrical or rectangular containers specially designed or prepared to house the source of uranium metal, the electron cannon and the collectors of the product and residues.
5.7.5. Supersonic relaxation tubers (SILMO)
Supersonic relaxation tubers, corrosion-resistant by UF6, specially designed or prepared to cool UF6 and gas mixtures up to 150 K or less.
5.7.6. Uranium pentafluoride collectors (SILMO)
Uranium pentafluoride collectors (UF5), specially designed or prepared, consisting of filter, impact or cyclone collector combinations and corrosion resistant in the UF5/UF6 medium.
5.7.7. UF6/gaz carrier compressors (SILMO)
Compressors specially designed or prepared for UF6 and carrier gas mixtures, intended for long-term operation in the atmosphere of UF6. The components of these compressors that are in contact with the process gas are made of or coated with corrosion-resistant materials by the UF6.
5.7.8. Tree seals (SILMO)
Specially designed or prepared fittings, with power and exhaust connections, to ensure reliable sealing of the shaft connecting the compressor rotor to the drive engine by preventing the process gas from escaping, or the air or gas from entering the compressor's inner chamber which is filled with the carrying UF6/gas mixture.
5.7.9. Fluoration systems (SILMO)
Systems specially designed or prepared to fluorine the UF5 (solid) in UF6 (gas).
5.7.10. Mass spectrometers
for UF6/ion sources (SILMO)
Spectrometers of magnetic or quadripolar mass specially designed or prepared, capable of taking live samples of the gas input, product or residue from the UF6 gas streams, and having all the following characteristics:
1. Unitary resolution power for atomic mass unit greater than 320;
2. Sources of nichrome or monel or nickel-plated ions;
3. Ionization sources by electronic bombardment;
4. Collector suitable for isotopic analysis.
5.7.11. Feeding systems/sampling systems
(SILMO)
Systems or equipment specially designed or prepared for enrichment plants, made or coated with corrosion-resistant materials by the UF6 including:
(a) Autoclaves, ovens and feeding systems used to introduce the UF6 into the enrichment process;
(b) Cold traps used to remove UF6 from the enrichment process for its subsequent transfer after warming;
(c) Solidification or liquefaction stations used to remove UF6 from the compression enrichment process and transition to liquid or solid state;
(d) "Product" or "Residues" stations for the transfer of the U6 into containers.
5.7.12. UF6 separation systems
(SILMO)
Systems specially designed or prepared to separate 1'UF6 from the carrying gas. The latter can be nitrogen, argon or other gas.
5.7.13. Laser systems (SILVA, SILMO and CRISLA)
Lasers or laser systems specially designed or prepared for the separation of uranium isotopes.
5.8. Systems, equipment and components specially designed or prepared for use in enrichment plants by separation of isotopes in plasma
5.8.1. Hyperfrequency and antenna energy sources
Hyperfrequency sources and antennas specially designed or prepared to produce or accelerate ions with the following characteristics: frequency greater than 30 GHz and average output power greater than 50 kW for ion production.
5.8.2. Exciting ion sticks
High frequency ion excitators specially designed or prepared for frequencies greater than 100 kHz and capable of supporting an average power greater than 40 kW.
5.8.3. Uranium plasma generator systems
Uranium plasma production systems specially designed or prepared, which can contain high-powered electron cannons with cluster or sweeping beams, providing a target power greater than 2.5 kW/cm.
5.8.4. Uranium Handling Systems Liquid Metal
Liquid metal handling systems specially designed or prepared for uranium or melted uranium alloys, including hollows and cooling equipment for hollows.
5.8.5. Collections of the product
and metal uranium residues
Collector assemblies of the product and residues specially designed or prepared for solid-state metal uranium. These collector assemblies are made or coated with heat-resistant and corrosion-resistant materials by metal uranium vapour, such as graphite coated with yttrium oxide or tantalum.
5.8.6. Separator module enclosures
Cylindrical containers specially designed or prepared for isotope separation enrichment plants in plasma and intended to house the source of uranium plasma, high frequency excitatory coil and product and residue collectors.
5.9. Systems, equipment and components specially designed and prepared for use in enrichment plants by electromagnetic process
5.9.1. Electromagnetic separators
Electromagnetic separators specially designed or prepared for the separation of uranium isotopes, and equipment and components for this separation, in particular:
(a) Ion sources.
Single or multiple sources of uranium ions, specially designed or prepared, including the steam source, ionizer and beam accelerator, made of suitable materials such as graphite, stainless steel or copper, and capable of providing a total ionization current equal to or greater than 50 mA.
(b) Ion collectors.
Collecting plates with slots and pockets (two or more), specially designed or prepared to collect enriched and impoverished uranium ion bundles, and made of suitable materials such as graphite or stainless steel.
(c) Vacuum speakers.
Vacuum enclosures specially designed or prepared for electromagnetic separators, made of suitable non-magnetic materials such as stainless steel and designed to operate at pressures of less than or equal to 0.1 Pa.
(d) Polar pieces.
Polar pieces specially designed or prepared, in diameter greater than 2 m, used to maintain a constant magnetic field inside the electromagnetic separator and to transfer the magnetic field between contiguous separators.
5.9.2. High voltage power supplies
High voltage power supplies specially designed or prepared for ion sources and having all the following characteristics: capable of continuously providing, for a period of 8 hours, an output voltage equal to or greater than 20,000 V with an output intensity equal to or greater than 1 A and a voltage variation of less than 0.01%.
5.9.3. Powers of magnets
Power supplies of high-intensity continuous current magnets specially designed or prepared and having all the following characteristics: capable of continuously producing, for a period of 8 hours, a current of intensity greater than or equal to 500 A at a voltage greater than or equal to 100 V, with variations of intensity and voltage less than 0.01 %.
6. Heavy water production or concentration plants, deuterium and deuterium compounds, and equipment specially designed or prepared for this purpose
Articles specially designed or prepared for heavy water production, either by the hydrogen water-sulphide exchange process or by the ammonia-hydrogen exchange process:
6.1. Hydrogen water-sulphide exchange towers
Exchange towers made of fine carbon steel (e.g. ASTM A516), having a diameter of 6 m (20 feet) and 9 m (30 feet), capable of operating at pressures greater than or equal to 2 MPa (300 psi) and having a corrosion thickness of 6 mm or more, specially designed or prepared for the production of heavy water through the hydrogen water-sulphide exchange process.
6.2. Blowers and compressors
Single-stage single-stage centrifugal blowers or compressors under low pressure (i.e. 0.2 MPa or 30 psi) for hydrogen sulphide circulation (i.e. a gas containing more than 70% H2S) specially designed or prepared for the production of heavy water through the hydrogen water-sulphide exchange process. These blowers or compressors have a flow capacity greater than or equal to 56 m3/s (120 000 SCFM) when operating at suction pressures greater than or equal to 1.8 MPa (260 psi), and are equipped with seals designed to be used in wet environment in the presence of H2S.
6.3. Ammonia-hydrogen exchange tours
Ammonia-hydrogen exchange towers of a height greater than or equal to 35 m (114.3 feet) having a diameter between 1.5 m (4.9 feet) and 2.5 m (8.2 feet) and capable of operating at pressures greater than 15 MPa (2 225 psi), specially designed or prepared for the production of heavy water through the ammonia-hydrogen exchange process. These towers also have at least one axial aperture at the edge of the same diameter as the cylindrical part, by which the tower internals can be inserted or removed.
6.4. Tower and floor pumps
Tower interns and floor pumps specially designed or prepared for towers used to produce heavy water through the ammonia-hydrogen exchange process. Turnovers include specially designed floor contactors that promote intimate contact between gas and liquid. Floor pumps include submersible pumps specially designed for liquid ammonia circulation in a contact floor inside the towers.
6.5. Ammonia crackers
Ammonia crackers with operating pressure greater than or equal to 3 MPa (450 psi) specially designed or prepared for heavy water production through the ammonia-hydrogen exchange process.
6.6. Infrared absorption analyzers
Infrared absorption analyzers allowing an online analysis of the hydrogen/deuterium ratio when deuterium concentrations are equal to or above 90%.
6.7. Catalytic burners
Catalytic burners for the conversion to heavy water of the enriched deuterium specially designed or prepared for the production of heavy water through the ammonia-hydrogen exchange process.
6.8. Complete heavy water concentration systems
or columns for such systems
Complete systems of heavy water concentration or columns for such systems, specially designed or prepared to obtain heavy water of reactor quality by the deuterium content.
7. Uranium and plutonium conversion plants for the manufacture of fuel elements and separation of uranium isotopes, as defined in sections 4 and 5 respectively, and equipment specially designed or prepared for this purpose
7.1. Uranium conversion plants
and equipment specially designed or prepared for this purpose
7.1.1. Systems specially designed or prepared for the conversion of uranium ore concentrates to UO3
7.1.2. Systems specially designed or prepared
for conversion of UO3 to UFO6
7.1.3. Systems specially designed or prepared
for conversion of UO3 to UO2
7.1.4. Systems specially designed or prepared
for conversion of UO2 to UF4
7.1.5. Systems specially designed or prepared
for conversion of UF4 to UF6
7.1.6. Systems specially designed or prepared
for conversion of U4 to metal
7.1.7. Systems specially designed or prepared
for conversion of UF6 to UO2
7.1.8. Systems specially designed or prepared
for conversion of UF6 to UF4
7.1.9. Systems specially designed or prepared
for conversion of UO2 to UC14
7.2. plutonium conversion plants
and equipment specially designed or prepared for this purpose
7.2.1. Systems specially designed or prepared
for conversion of plutonium nitrate to oxide
7.2.2. Systems specially designed or prepared
for production of metal plutonium
Done on 3 February 2011.
Nicolas Sarkozy
By the President of the Republic:
The Prime Minister,
François Fillon
The Minister of State,
Minister for Foreign Affairs
and European,
Michèle Alliot-Marie
