Decree No. 375 / 2016 Coll.
Decree on selected items in the nuclear field
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Effective from 01.01.2017
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01.01.2017
18.11.2016
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375
DECLARATION
of 7 November 2016
on selected nuclear items
The State Office for Nuclear Safety sets out, pursuant to § 236 of Act No. 263 / 2016 Coll., the Atomic Act, for the implementation of § 18 (5), § 24 (7), § 25 (2) (d), § 166 (6) (d) and § 169 (4):
Details of the end-use declaration of the selected item in the nuclear field
The final use of the selected item in the nuclear field in the event of its transfer shall include:
(a) the quantity, name and specification of the selected item in the nuclear area under this decree;
(b) an indication of the method of end-use;
(c) the date of the transfer;
(d) details of the notifier, namely:
1. the name and, where applicable, the names and surnames if they are natural persons; or
2. name, if it is a legal person,
(e) the address of the end-user's registered office, permanent residence or residence;
(f) end-user obligation
1. not to use the selected item in or part of the nuclear area for any purpose contrary to the Treaty on the Non-Proliferation of Nuclear Weapons;
2. ensure that the selected nuclear item or part thereof is not misused for military purposes; and
3. ensure the notification of further transfer of the selected item in the nuclear field or part thereof within the Czech Republic of the Office; and
(g) the estimated date of notification of the transfer of the selected item in the Authority's nuclear area, determined to be made within 30 working days of the transfer.
Requirements for the content of the documentation for the authorised activity which is the import or export or transit of a nuclear item selected in the nuclear field
The content of the documentation for the authorised activity, which is the import, export or transit of the nuclear item, which is a selected item in the nuclear field, shall be the set of data determined in accordance with § 3 (1) (a) to (d).
Scope, manner and duration of retention of registered nuclear data collected in the nuclear field and deadlines for their transmission to the Authority
(1) In the case of export or import or transit of a selected item in the nuclear area, the data shall be recorded to the following extent:
(a) the quantity, name and specification of the selected item in the nuclear area under this decree;
(b) the name and address of the supplier's and end-user's registered office of the selected items in the nuclear field, if they are legal persons, or their name, or names, as appropriate, and the surname and address of the permanent residence or residence, if they are natural persons;
(c) the contract application and other commercial documents;
(d) the date of import, export or transit of the selected item in the nuclear field;
(e) the date on which the imported or exported or associated selected nuclear item entered the territory of the Czech Republic or left the territory of the Czech Republic;
(f) in the case of imports, an indication of when the selected item in the nuclear area was transmitted to the end user; and
(g) the end-user's written confirmation of taking over the selected item in the nuclear area.
(2) The holder of the authorisation to export or import or transit the selected item in the nuclear area shall notify the Office of the registered data referred to in paragraph 1.
(a) points (a) to (f) within 5 working days of completion of the export, import or transit; and
(b) point (g) within 30 working days of the date of transmission of the selected item in the nuclear area to the end user.
(3) The holder of the authorisation to export or import or transit the selected item in the nuclear area shall keep the registered data for at least 3 years from the date of implementation.
List of selected nuclear items
The list of selected items in the nuclear area is set out in Annex 1 to this Decree.
Model end-user statement
The model of the end-user declaration of the selected item in the nuclear area on its import is set out in Annex 2 to this decree.
Notification
This Decree was notified in accordance with Directive (EU) 2015 / 1535 of the European Parliament and of the Council of 9 September 2015 laying down a procedure for the provision of information in the field of technical and information society services.
Efficacy
This Decision shall enter into force on 1 January 2017.
President:
Ing. Drábová, Ph.D., v. r.
Příloha č. 1
Annex No 1 to Decree No 375 / 2016 Coll.
ANNEX
SELECTED MATERIALS, EQUIPMENT AND TECHNOLOGY IN THE NUCLEAR AREA
1. Nuclear reactors and specially designed or modified equipment and components for the operation of nuclear reactors
Nuclear reactors of different types according to the type of moderator used, the spectrum of neutrons, the type of refrigerant used or their function or type. In particular, light water, heavy water or graphite or nuclear reactors may be used as a moderator without a moderator. According to the neutron spectrum, nuclear reactors are hot or fast. The coolant of nuclear reactors is water, liquid metal, fused salt or gas. Nuclear reactors shall be divided according to their function or type into energy reactors, research reactors and test reactors.
All items of this point include all listed types of nuclear reactors. This item does not cover fusion reactors.
1.1. Complete nuclear reactors
Nuclear reactors capable of maintaining a controlled chain fission reaction.
The nuclear reactor includes items that are or are directly associated with the reactor vessel, equipment controlling the power of the core and components that contain, come into direct contact with, or control the primary circuit coolant.
1.2. Reactor containers
Metal containers or their main workshops manufactured parts specially designed or modified for the location of the nuclear reactor active zone specified in 1.1 and reactor assemblies specified in 1.8.
b.
The reactor vessel lid is included in item 1.2 as the main workshops manufactured by the reactor vessel component.
1.3. Nuclear reactor weighing machines
Manipulative equipment, specially designed or modified to bind or remove nuclear fuel from the nuclear reactor specified in 1.1., capable of carrying out the exchange of nuclear fuel in service or using technically complex location or direction elements that allow the execution of a complex of operations during the nuclear fuel exchange during the nuclear reactor shutdown when direct observation or access to nuclear fuel is not usually possible.
1.4. Nuclear reactor control rods and related equipment
Specially designed or prepared rods, their supporting or hanging structures, rod drives and their guide tubes for the control of the fission process in the nuclear reactor specified in 1.1.
1.5. Nuclear reactor pressure pipes
Pipe tubes specially designed or prepared to contain the fuel cells and primary coolant of the nuclear reactor specified in 1.1. Pressure tubes form part of fuel channels designed to operate at a higher pressure which may exceed 5 MPa.
1.6. Coverage of nuclear fuel
Zirconium tubes or pipes of zirconium alloys or pipe assemblies, specially designed or prepared for use as nuclear fuel coverage in a nuclear reactor specified in 1.1., in quantities exceeding 10 kg.
Zirconium pressure pipes fall under entry 1.5., heavy water reactor tubes fall under heading 1.8.
Metal tubes of zirconium or zirconium alloys intended for use in nuclear reactors have a ratio of hafnia and zirconium typically less than 1: 500.
1.7. Pumps or circulators of primary cooling medium
Pumps or circulators specially designed or modified to provide the primary coolant of a nuclear reactor as specified in 1.1. Specially designed or modified pumps or circulators include pumps for a water-cooled nuclear reactor, gas-cooled nuclear reactor circulators and electromagnetic or mechanical pumps for a liquid-metal nuclear reactor.
These devices may include pumps with complicated sealing systems or multiple sealing systems to prevent leakage of primary cooling medium, hermetic motor pumps and centrifugal pumps.
Such equipment shall include, in particular, pumps certified in accordance with Part III, Section I, subpart NB of the Code of the American Engineering Society or similar standards.
1.8. Construction of nuclear reactors
Nuclear reactor assemblies specially designed or modified for use in a nuclear reactor specified in 1.1. b.
Nuclear reactor assemblies are important structures within the reactor vessel that have one or more functions such as strengthening and fixation of the core, directing the primary coolant flow, providing radiological shielding of the reactor vessel and controlling the handling of tools and equipment within the core.
1.9. Heat exchangers
1.9.1. Parogenerators specially designed or modified for use in the primary or inserted cooling circuit of a nuclear reactor specified in 1.1.
1.9.2. Other heat exchangers specially designed or modified for use in the primary cooling circuit of a nuclear reactor specified in 1.1.
Parogenerators are specially designed or prepared to transfer the heat generated in the nuclear reactor to the steam water. In the case of a fast reactor that works with the cooling loop as an intermediate step, the steam generator is in the inserted circuit.
For gas-cooled nuclear reactor, the heat exchanger may be used to transfer heat to the secondary gas loop that drives the gas turbine. This item does not cover heat exchangers for reactor support systems such as emergency cooling systems or breakdown heat cooling systems.
1.10. Neutron Detectors
Specially designed or modified neutron detectors for determining neutron flux levels within the nuclear reactor active zone specified in 1.1.
This item includes detectors within and outside the active zone that measure neutron flow levels over a wide range, usually from 104 neutrons per cm2 / s to 1010 neutrons per cm2 / s or greater.
Detectors outside the active zone include devices outside the active zone of the nuclear reactor specified in 1.1., which are located within the biological shielding.
1.11. External thermal shielding
External heat shields specially designed or modified for use in a nuclear reactor specified in 1.1. for reducing heat loss and protecting the container.
The external heat shields are significant structures located over the reactor vessel which reduce the heat loss of the nuclear reactor and lower the temperature within the container.
2. Non-nuclear materials for nuclear reactors
2.1. Deuterium and heavy water
Deuterium, heavy water and other deuterium compounds in which the ratio of deuterium atoms to hydrogen atoms exceeds 1: 5 000, for use in the nuclear reactor specified in 1.1., in quantities exceeding 200 kg of deuterium atoms for any recipient country at any time within 12 months.
2.2. Graphite nuclear purity
Graphite with a purity greater than 5 ppm boron equivalent and a density greater than 1,5 g / cm3, for use in a nuclear reactor specified in 1.1., in a quantity exceeding 1 kg. The boron equivalent (BE) is determined experimentally or is calculated as the sum of BEZ for impurities (except BEucarbon, since carbon is not considered as impurity) including boron where: BEZ (ppm) = CF x concentration of Z element (in ppm), CF is the conversion factor defined as follows:
where δB and δZ are effective cross-sections of the capture of heat neutrons (in bars) of boron in nature and element Z and AB and AZ are atomic mass of boron in nature and element Z.
3. Race for the reprocessing of irradiated fuel cells and equipment specially designed or modified for this purpose
Plant for the reprocessing of irradiated fuel cells or parts thereof, which means equipment for cutting irradiated fuel cells, dissolving nuclear fuel, liquid extraction and storage of technological solutions. The plants may also include equipment for the thermal denitration of uranium nitrate, for the conversion of plutonium nitrate to oxide or to metal and for the treatment of liquid waste of fissile products into a form suitable for long-term storage or storage.
The items corresponding to the term "equipment specially designed or modified for the reprocessing of irradiated fuel elements' include:
3.1. Machines for dividing irradiated fuel cells
Remote controlled equipment specially designed or modified for use in a plant for the reprocessing of irradiated fuel elements, designed for cutting, cutting or cutting irradiated fuel cartridges, bundles or rods. These devices upset the coating of nuclear fuel and thus prepare irradiated nuclear material for dissolution. Specially designed machine shears are most frequently used, but other devices, especially lasers, may be used.
3.2. Solvent tanks
Tanks secured against critical achievement, in particular small diameter, ring or plate design, specially designed or modified for use in a plant for the reprocessing of irradiated fuel elements which are designed to dissolve irradiated nuclear fuel in nitric acid, are resistant to hot, highly corrosive liquids and can be remotely filled and operated.
Solvent tanks normally absorb cut-off irradiated nuclear fuel. In these containers, irradiated nuclear material is dissolved in nitric acid and the remaining insoluble parts are removed from the technological flow.
3.3. Liquid extractors and liquid extraction equipment
Specially designed or prepared extractors, such as charge and pulse columns, mixing and settling tanks or centrifugal reactors, for use in irradiated fuel cell reprocessing plants. Liquid extractors shall be resistant to corrosion by nitric acid.
Liquid extractors are usually manufactured according to the strictest standards, including special welding, control, quality assurance and quality control, from low-carbon stainless steel, titanium, zirconium and other high-quality materials.
Liquid extractors take the irradiated nuclear fuel solution from solvent tanks and organic solutions for uranium, plutonium and fissile products. The liquid extraction equipment is normally designed to meet strict operating parameters such as long service life without maintenance or adaptability requirements aimed at easy replacement, simplicity of operation and controls and flexibility regarding operational variables.
3.4. Containers for storage of chemicals or containers
Specially designed or prepared storage vessels or storage tanks for use in a irradiated nuclear fuel reprocessing plant. These containers or containers shall be resistant to corrosion by nitric acid. They are usually made of low-carbon stainless steel, titanium, zirconium or other high-quality materials. Containers or containers may be designed for remote control and maintenance and may have the following parameters to prevent criticism: walls or internal structures corresponding to a boron equivalent of at least 2%, a maximum diameter of 175 mm for cylindrical containers or a maximum width of 75 mm for each plate or ring vessel.
Chemical or storage containers are used for further processing of 3 major flows from the extraction operation: pure uranium nitrate solution is concentrated by evaporation and is converted into uranium oxide in the subsequent denitration process, which is reused in the nuclear fuel cycle. The high radioactive solution of fissile products is normally concentrated by evaporation and stored in the form of liquid concentrate. This concentrate may then be evaporated and converted into a form suitable for storage or disposal. The pure plutonium nitrate solution is concentrated and stored until it is transformed for further technological steps. In particular, the storage containers for plutonium solutions or storage tanks intended for the storage of plutonium solutions are designed to avoid critical problems caused by changes in the concentration and form of the solution.
3.5. Neutron measurement systems for process control
Neutron measurement systems specially designed or modified for integration and use with automated operation control systems in irradiated fuel cell reprocessing plants. These systems have the capability of active and passive neutron measurement and resolution for determining the amount and composition of fissile materials. The system consists of a neutron generator, a neutron detector, amplifiers and electronics for signal processing.
This item does not cover neutron detection and measurement equipment designed for warranty purposes and for the keeping of records of nuclear materials or other applications not related to integration and use with automated operation control systems in irradiated fuel cell reprocessing plants.
4. Fuel cell plants for nuclear reactors and equipment specially designed or modified for this purpose
Oxide-based fuel cell plants and parts thereof, such as tablet pressing, sintering, crushing and sorting plants and MOX nuclear fuel plants. This item includes equipment that comes into direct contact with nuclear material, directly processes or controls the production flow of nuclear material, hermetically close nuclear material within the scope of coverage, controls the integrity of coverage and hermetisation, controls the finishing of hermetically sealed nuclear fuel, or is used to complete fuel cells for nuclear reactors.
The term "equipment specially designed or modified for the production of fuel elements' includes, for example, fully automated control stents specially designed or modified for the control of final dimensions and surface defects of tablets, automatic welding machines specially designed or modified for the welding of fuel cell or beam end covers, systems specially designed or modified for the production of nuclear fuel coverage, and automatic testing and control stents specially designed or modified for the integrity of finished fuel elements or rods; These usually include X-ray test devices for cell or cord welds, helium leakage detection devices from pressurised cells or rods, and gamma-scan devices for cells or rods to verify the accuracy of their filling with fuel pellets.
5. Plant for the separation of isotopes of natural uranium, depleted uranium or special fissile material and equipment other than analytical apparatus specially designed or modified for this purpose
Plant, plant and technology for the separation of uranium isotopes and plants, equipment and technology for the separation of isotopes of other elements, excluding plants, equipment and technology for the separation of isotopes of other elements using the electromagnetic separation process.
Items corresponding to "equipment other than analytical instruments specially designed or modified for the separation of uranium isotopes' include:
5.1. Gas centrifuges, assemblies and components specially designed or modified for use in gas centrifuges
Gas centrifuges consisting of a thin-wall cylinder with a diameter of between 75 mm and 650 mm located in a vacuum environment and rotating at a high circumference speed, of 300 m / s or more, around a vertical axis. The design materials of rotating components shall have a high strength relative to density in order to achieve the required speed. The rotor assembly unit and its individual components shall be manufactured with very small tolerances to reduce the imbalance of operation. The uranium enrichment gas centrifuge is characterised by a rotor chamber with a rotating disc deflector and a stationary tube assembly for the supply and supply of UF6 gas, equipped with at least three separate channels, two of which are connected with blades extending from the rotor axis to the rotor chamber circumference. Components include critical parts that do not rotate and which, although specially designed, are not made from special materials.
5.1.1. Rotary components
5.1.1.1. Complete rotor assemblies
Thin-wall cylinders or a series of interconnected thin-wall cylinders which are made of high strength to density ratio materials. If the cylinders are connected, the connections are obtained by flexible waves or rings as described in 5.1.1.3. The rotor is equipped with an internal deflector and the end caps described in 5.1.1.4. and 5.1.1.5. The complete assembly can only be supplied partially assembled.
5.1.1.2. Rotor tubes
a.
5.1.1.3. Rings or cords
Components specially designed or prepared to allow the fitting of a rotor tube support structure or to join a series of rotor tubes together. The wave is a rolled short cylinder with a diameter of 75 mm to 650 mm with a maximum wall thickness of 3 mm, made of material with a high strength to density ratio.
5.1.1.4. Deflectors
Circular components with a diameter between 75 mm and 650 mm, specially designed or prepared to be mounted inside a centrifuge rotor tube, designed to separate the sampling chamber from the main separation chamber and in some cases to assist the circulation of UF6 gas within the main separation chamber of the rotor tube. They are made of materials with a high strength to density ratio.
5.1.1.5. Top and bottom end caps
Circular components with a diameter between 75 mm and 650 mm specially designed or prepared to close the ends of the rotor tube and to hold UF6 inside the rotor tube, which in some cases also act as supports, maintain or contain as an integral part of the top bearing which is the top cap, or carry the rotational parts of the engine and the bottom bearing which is the bottom cap. They are made of materials with a high strength to density ratio.
For the rotary parts of centrifuges specified in 5.1.1.1. to 5.1.1.5. high-tenacity steel having a tensile strength of 1,95 GPa or more, aluminium alloys having a tensile strength of 0,46 GPa or more, or fibrous materials, suitable for use in composite structures, having a specific modulus of 3,18 × 106 m or more and a specific tensile strength of 7,62 × 104 m or more. The measurement module is the Young module in N / m2 divided by the specific mass in N / m3; the specific tensile strength limit is the tensile strength limit in N / m2 divided by the specific mass in N / m3.
5.1.2. Non-moving components
5.1.2.1. Magnetic suspension bearings
5.1.2.1.1. Specially designed or prepared bearing assemblies, consisting of ring magnets suspended inside a housing containing a damping medium. The housing is made of UF6-resistant material which, for this item, means copper, copper alloys, stainless steel, aluminium, aluminium oxide, aluminium alloys, nickel or nickel alloys containing at least 60% nickel and hydrofluorocarbons polymers. Magnetic pairs with pole attachments or second magnet are connected to the top cap specified in 5.1.1.5. The magnet can be ring shaped, with the maximum ratio between the outer diameter and the inner diameter equal to 1.6: 1. Magnet may have an initial permeability of at least 0,15 H / m, a minimum remanence of 98,5% or more and an energy yield of more than 80 kJ / m3. In addition to the usual material properties, the variation of the magnetic axis from the geometric axis is limited by very small tolerances, less than 0,1 mm, or the material of the magnet is highly homogeneous.
5.1.2.1.2. Active magnetic bearings specially designed or modified for use with gas centrifuges. These bearings usually have the following characteristics: they are designed to maintain centered rotor rotation of at least 600 Hz and have a connection to a reliable power supply or backup power supply to maintain the function for more than 1 hour.
5.1.2.2. Bearings and dampers
Specially designed or modified bearings incorporating a pivot or cap assembly mounted on a silencer. The rotary pin is usually a hardened steel shaft with a hemisphere at one end and a fixture for the lower cap, as specified in 5.1.1.5., at the end of the other. A hydrodynamic bearing may be connected to the shaft. The lid is a pellet with a semi-spherical socket on one of the surfaces. These components may be supplied separately from the silencer.
5.1.2.3. Molecular pumps
Specially designed or prepared cylinders having internal machined or extruded helical grooves and internal machined openings. The usual dimensions are as follows: internal diameter between 75 mm and 650 mm, wall thickness at least 10 mm, with a ratio of length to diameter of 1: 1 or greater. The tracks have a typical rectangular cross-section and depth of 2 mm or more.
5.1.2.4. Engine stators
Specially designed or modified ring stators for high-speed multi-phase AC-motors, modified for synchronous operation in a vacuum at a frequency of 600 Hz or more and a power output of at least 40 VA. The stators may consist of multi-phase winding on a laminated iron core with small losses consisting of thin layers usually of a thickness of 2 mm or less.
5.1.2.5. Centrifugal cases
Components specially designed or prepared to accommodate gas centrifuge rotor tube assemblies. The cases consist of a solid cylinder with a wall thickness of up to 30 mm with precision machined ends for bearing placement and one or more mounting flanges. Worked ends are parallel to each other and perpendicular to the longitudinal axis of the cylinder with a deviation of less than or equal to 0,05 °. The housing can also be of a honeycomb type for storing several rotor units.
5.1.2.6. Shoulders
Specially designed or prepared tubes for the extraction of UF6 gas from a rotor tube based on the effect of a Pitot tube with an orifice oriented in the direction of the gas circuit current within the rotor, for example by bending the end of a radially positioned tube which can be fixed to the central gas discharge system.
5.2. Auxiliary systems, equipment and components specially designed or modified for use in gas centrifuge enrichment plants
5.2.1. Power supply and discharge systems "product" and "residue"
Specially designed or modified technological systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6 gas. For this item, materials resistant to corrosion by UF6 are copper, copper alloys, stainless steel, aluminium, aluminium oxide, aluminium alloys, nickel or nickel alloys containing at least 60% nickel and fluorinated hydrocarbon polymers.
5.2.1.1. Power autoclaves, furnaces or systems used to bring UF6 into the enrichment process.
5.2.1.2. Desublimators, freezers or pumps used to remove UF6 from the enrichment process for subsequent heating transport.
5.2.1.3. Solidifying or liquefying stations for the removal of UF6 from the enrichment process by compression and conversion of UF6 into liquid or solid.
5.2.1.4. The "product 'and" residues' stations used to fill UF6 into containers.
5.2.2. Machine pipe systems of collectors
Specially designed or modified collector piping and collector systems (hereinafter referred to as "collector ') for the transport of UF6 within centrifugal cascades. The piping network is usually a type of triple collector system where each centrifuge is connected to each collector. This arrangement is repeated many times. These systems are made of or protected by corrosion resistant materials of UF6 and are designed to meet the requirements of very high vacuum standards and very high purity. For this item, materials resistant to corrosion by UF6 are copper, copper alloys, stainless steel, aluminium, aluminium oxide, aluminium alloys, nickel or nickel alloys containing at least 60% nickel and fluorinated hydrocarbon polymers.
5.2.3. Special closing and regulating valves
Specially designed or prepared valves include, for example, bellows-sealed valves, quick-closing valves or quick-moving valves.
5.2.3.1. The shut-off valves specially designed or modified for use in the supply, product or residual UF6 gas streams of individual gas centrifuges.
5.2.3.2. Bellows sealed valves, manual or automatic, closing or regulatory, made of or protected by materials resistant to corrosion by UF6, with an internal diameter of 10 to 160 mm, specially designed or prepared for use in major or auxiliary gas centrifuge enrichment plant systems. For this item, materials resistant to corrosion by UF6 are copper, copper alloys, stainless steel, aluminium, aluminium oxide, aluminium alloys, nickel or nickel alloys containing at least 60% nickel and fluorinated hydrocarbon polymers.
5.2.4. Mass spectrometers for UF6 analysis and ion sources
Specially designed or modified mass spectrometers capable of performing on-line sampling of UF6 gas streams having:
5.2.4.1. the ability to measure ions with an atomic mass of 320 units or more and a resolution of better than 1: 320;
5.2.4.2. ion sources made of or coated with nickel, nickel alloys and copper containing at least 60% nickel by weight or nickel and chromium alloys;
5.2.4.3. ion sources with electron bombardment ionization; and
5.2.4.4. Collector system suitable for isotopic analysis.
5.2.5. Frequency changers
Frequency changers, also known as converters or inverters, specially designed or modified for the supply of engine stators specified in 5.1.2.4., or parts, components and assemblies of such frequency converters, having the following characteristics:
5.2.5.1. a multi-phase output of 600 Hz or more; and
5.2.5.2. high stability with frequency control better than 0,2%.
5.3. Specially designed or prepared assemblies and components for use in gas diffusion enrichment
Items corresponding to the term "specially designed or prepared assemblies and components for use in gas diffusion enrichment 'include:
5.3.1. Gas diffusion bulkheads and bulkheads
5.3.1.1. a.
5.3.1.2. Specially modified compounds or powders for the manufacture of these filters. Such compounds and powders contain nickel or its alloys with a minimum nickel content of 60%, aluminium oxide or to UF6 resistant to fully fluorinated hydrocarbon polymers with a purity by weight of 99,9% or more, a particle size of less than 1 × 10- 6 m and a high degree of particle size uniformity which are specially designed for the manufacture of gas diffusion bulkheads.
5.3.2. Diffuser lockers
Specially designed or prepared hermetically sealed containers in which diffuse bulkheads are located, made of or coated with copper, copper alloys, stainless steel, aluminium, aluminium oxide, nickel or nickel-containing materials resistant to corrosion by UF6.
5.3.3. Compressors and gas blowers
Specially designed or prepared compressors or gas blowers with a minimum suction capacity of 1 m3 / min UF6 and a discharge pressure of up to 500 kPa, designed for long-term use in UF6, as well as individual assemblies of such compressors and gas blowers. These compressors and gas blowers have a pressure ratio of 10: 1 or less and are made of or coated with copper, copper alloys, stainless steel, aluminium, aluminium oxide, nickel or nickel-containing materials resistant to corrosion by UF6.
5.3.4. shaft sealing
Specially designed or modified vacuum seals that provide sealing of the inlet and outlet flanges and serve for sealing the shaft connecting the compressor rotor or gas blower with the propulsion engine and ensuring a reliable sealing of the internal chamber of the compressor or gas blower that is filled with UF6. Such seals are normally designed for a balancing gas penetration rate of less than 1000 cm3 / min.
5.3.5. Heat exchangers for UF6 cooling
Specially designed or prepared heat exchangers made of or coated with copper, copper alloys, stainless steel, aluminium, aluminium alloys, aluminium oxide, nickel or nickel alloys containing at least 60% nickel and fluorinated hydrocarbon polymers. They are designed for the maximum rate of pressure change due to leakage of less than 10 Pa per hour at a pressure difference of 100 kPa.
5.4. Specially designed or modified auxiliary systems, equipment and components for use in gas diffusion enrichment plants
The items below come into direct contact with UF6 technology gas or directly regulate the flow inside the cascade. They meet the requirements of very high vacuum standards and very high purity. The measuring, control and control systems ensure strict and continuous maintenance of vacuum in all technological systems, automatic emergency protection and precise automatic regulation of gas flow. All surfaces that come into contact with the technological gas are made of or coated with materials resistant to UF6.
5.4.1. Power supply and removal systems for "product" and "residue"
a.
5.4.1.1. Power autoclaves, furnaces or systems used to bring UF6 to the enrichment process.
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Regulation Information
| Citation | Decree No. 375 / 2016 Coll., on selected items in the nuclear field |
|---|---|
| Regulation Type | Order |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 18.11.2016 |
|---|---|
| Effective from | 01.01.2017 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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