Decree No. 179 / 2002 Coll.
Decree of the State Office for Nuclear Safety establishing a list of selected items and dual-use items in the nuclear field
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09.05.2002
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179
DECLARATION
State Office for Nuclear Security
of 19 April 2002
establishing a list of selected items and dual-use items in the nuclear field
The State Nuclear Safety Authority provides, in accordance with § 47 (7), for the implementation of § 2 (b). (j) points 2 and 3 of Act No. 18 / 1997 Coll., on the Peaceful Use of Nuclear Energy and Ionising Radiation (Atomic Act) and on the Amendment and Addition of Certain Laws, hereinafter referred to as "the Act":
Subject matter and scope of the adjustment
(1) This Decree sets out a list of selected items [§ 2 (j) (2) of the Act] and dual-use items [§ 2 (j) (3) of the Act] in the nuclear field.
(2) The list of selected items is set out in Annex 1 to this Decree and the list of dual-use items is set out in Annex 2 to this Decree.
Repeal
Decree No. 147 / 1997 Coll., establishing a list of selected items and dual-use items in the nuclear field, is hereby repealed.
Efficacy
This Decree shall take effect on 1 June 2002.
President:
Ing. Drábová v. r.
Příloha č. 1
Annex No 1 to Decree No 179 / 2002 Coll.
LIST OF SELECTED ITEMS
(SELECTED MATERIALS, EQUIPMENT AND TECHNOLOGY IN NUCLEAR AREA)
SUBJECT TO CONTROL SCHEME FOR IMPORTS, EXPORT AND TRANSPORT
the list is drawn up in accordance with the document of the International Atomic Energy Agency INFCIRC / 254 / Rev. 5 / Part 1
0. Packaging files for irradiated nuclear fuel and hot cells
0.1. Packaging files for irradiated fuel
Packaging packages for the transport and / or storage of irradiated nuclear fuel, which include chemical, thermal and radiation protection and remove disintegration heat during handling, transport and storage.
0.2. Hot chambers
Hot cells or interconnected hot cells with a total capacity of at least 6 m3 with a shielding equivalent to or greater than 0,5 m concrete, a density of 3,2 g / cm3 or more, equipped with a remote control device.
1. Nuclear reactors and specially designed or modified equipment and components for the operation of nuclear reactors
1.1. Complete nuclear reactors
Nuclear reactors capable of maintaining a critical controlled chain reaction of fission, except zero power reactors. Zero power reactors are defined as reactors with a designed maximum annual plutonium production not exceeding 100 g.
Note
The nuclear reactor includes items that are inside or directly associated with the reactor vessel, equipment controlling the power of the core and components that contain, come into direct contact or control the circulation of the primary circuit coolant. Those reactors that can be modified to produce significantly more than 100 g of plutonium per year cannot be excluded. Reactors designed for continuous operation at a significant power level, regardless of their plutonium production capacity, are not considered to be "zero power reactors."
1.2. Reactor containers
Metal containers or their main workshops manufactured parts specially designed or modified for the location of an active nuclear reactor zone as defined in paragraph 1.1., as well as reactor assemblies as defined in paragraph 1.8.
Note
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
Manipulating equipment specially designed or modified for weighing or removing fuel from a nuclear reactor as defined in paragraph 1.1.
Note
The above items are capable of carrying out fuel exchange in operation or of using technically complex elements for location or direction which allow the execution of a complex of operations during the fuel exchange during the nuclear reactor shutdown when direct observations or access to fuel are 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 a nuclear reactor as defined in paragraph 1.1.
1.5. Nuclear reactor pressure pipes
Pipe tubes specially designed or prepared to contain fuel elements and primary reactor coolant as defined in paragraph 1.1 above at operating pressures exceeding 5,07 MPa.
1.6. Zirconium tubes
Metal zirconium and alloys, in the form of tubes or pipe assemblies, specially designed or modified for use in a nuclear reactor as defined in paragraph 1.1, in quantities exceeding 500 kg for any country receiving 500 kg at any time during 12 months and for which the hafnia-zirconium weighting ratio is less than 1: 500.
1.7. Primary coolant pumps
Pumps specially designed or modified to ensure the circulation of the primary coolant of nuclear reactors as defined in paragraph 1.1.
Note
Specially designed pumps may include complicated sealing or multiple sealing systems designed to prevent primary coolant leakage, hermetic motor pumps and centrifugal pumps. This definition includes pumps of category NC-1 or equivalent standards.
1.8. Construction of nuclear reactors
Nuclear reactor assemblies specially designed or modified for use in the nuclear reactor as defined in paragraph 1.1, including the core structure, control rods guide tubes, heat shielding, dampening divisions, core grid boards and diffuser plates.
Note
Nuclear reactor assemblies are important structures within the reactor vessel that have one or more functions such as strengthening and fixation of the active zone, directing the primary coolant flow, ensuring radiological shielding of the reactor vessel and controlling the handling of tools and equipment within the active zone.
1.9. Heat exchangers
Heat exchangers (steam generators) specially designed or modified for use in the primary cooling circuit of a nuclear reactor as defined in paragraph 1.1.
Note
Parogenerators are specially designed or modified equipment for the conversion of heat generated in the reactor (primary) into steam. In the case of a liquid metal fast-moving reactor that operates with a liquid metal cooling loop as an intermediate step, heat exchangers transferring heat between the primary and the interstep cooling circuit are understood as falling within the scope of the controlled, as additional parts to the steam generators. The control range of this paragraph does not include temperature exchangers for emergency cooling systems or cooling systems for breakdown heat.
1.10. Neutron detection and measurement apparatus
Specially designed or modified neutron detection and measurement instruments for determining neutron flux levels within the reactor active zone as defined in paragraph 1.1.
Note
This item includes internal and external instruments which measure neutron flow levels over a wide range, typically from 104 neutrons per cm2 / s to 1010 neutrons per cm2 / s or more. The external devices are those outside the reactor active zone as defined in paragraph 1.1., but located within the biological shielding.
2. Non-nuclear materials for reactors
2.1. Deuterium and heavy water
Deuterium, heavy water (deuterium oxide) and other deuterium compounds in which the ratio of deuterium atoms to hydrogen atoms exceeds 1: 5000, intended for use in the nuclear reactor defined in paragraph 1.1 above, in excess of 200 kg of deuterium atoms for any recipient country at any time within 12 months.
2.2. Graphite nuclear purity
Graphite of a purity better than 5 ppm boron equivalent and a density greater than 1,50 g / cm3 for use in a nuclear reactor as defined in paragraph 1.1., in quantities exceeding 30 tonnes for any recipient country at any time within 12 months.
Note
The boron equivalent (BE) can be determined experimentally or is calculated as the sum of BEz for impurities (except BEuhík because carbon is not considered to be impurity) including boron where:
BEZ (ppm) = CF x concentration of element Z (in ppm);
CF is the conversion factor: (deltaz x AB) divided by (deltaB x Az);
deltaB and deltaz are the effective cross-section of the capture of heat neutrons (in bars) of boron found in nature, respectively element Z; and AB and Az are atomic mass of boron found in nature, respectively element Z.
3. Race for the reprocessing of irradiated fuel cells and equipment specially designed or modified for this purpose
Note
The reprocessing of irradiated nuclear fuel separates plutonium and uranium from highly radioactive fissile products and other transurane elements. Such separation may be carried out by different technological processes. Over the years, Purex has become the most widely used and respected process. Purex includes dissolution of irradiated nuclear fuel in nitric acid and subsequent separation of uranium, plutonium and fissile products by liquid extraction using tributylphosphate in an organic solvent. Purex plants use listed or similar technology operations: cutting irradiated fuel cells, dissolving fuel, liquid extraction and storage of technological solutions.
There may also be 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 fissile products into a form suitable for long-term storage or storage. However, the specific types and arrangements of the equipment on which these operations are carried out may differ in different Purex plants for the following reasons: according to the type and quantity of irradiated fuel intended for reprocessing and intended loading with regenerated materials, as well as the safety and maintenance philosophy included in the plant project.
The reprocessing plant for irradiated fuel cells includes equipment and components that normally come into direct contact and directly control irradiated fuel flows and the main flows of nuclear material and technological solutions of fissile products.
These processes, including complete systems for the conversion of plutonium and the production of metal plutonium, are closely related to measures to prevent criticism (e.g. by adjusting the geometric layout), exposure (e.g. by shielding) and toxicity hazards (e.g. the use of protective packaging).
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
Note
This device disrupts the fuel coating and thus prepares irradiated nuclear material for dissolution. Specially designed machine scissors are most often used, but modern equipment such as lasers can also be used.
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.
3.2. Solvent tanks
Note
Dismembered spent fuel usually progresses to solvent tanks. In these containers, irradiated nuclear material is dissolved in nitric acid and the residue of the fuel coating is removed from the technological process.
Tanks secured against critical (e.g. small diameter, ring or plate design) specially designed or modified for use in reprocessing plants are designed for the dissolution of irradiated nuclear fuel and are resistant to hot, highly corrosive liquids and can be remotely filled and operated.
3.3. Liquid extractors and liquid extraction equipment
Note
Both irradiated fuel solution from solvent tanks and organic solutions that separate uranium, plutonium and fissile products enter liquid extractors. The liquid extraction equipment is normally designed to meet strict operating parameters such as long service life without maintenance requirements or easy interchangeability, ease of operation and operation and flexibility when changing technological conditions.
Specially designed or prepared extractors, such as charge and pulse columns, mixing and settling tanks or centrifugal reactors, are designed 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 extremely strict standards (including special welding, control, quality assurance and quality control) from low-carbon stainless steel, titanium, zirconium and other high-quality materials.
3.4. Containers for storage of chemicals or containers
Note
Three main flows of technological solutions are derived from the extraction operation. Storage containers or containers are used for further processing of all three flows as follows:
(a) Pure uranium nitrate solution is concentrated by evaporation and progresses to denitration operation where it is converted into uranium oxide. This oxide is reused in the nuclear fuel cycle.
(b) A highly radioactive solution of fissile products is usually concentrated by evaporation and stored as a liquid concentrate. This concentrate may subsequently be evaporated and converted into a form suitable for storage or storage.
(c) The solution of pure plutonium nitrate is concentrated and stored until it is transmitted to the next stage of the technological process. In particular, storage containers or cartridges for plutonium solutions are designed to avoid critical problems resulting from changes in the concentration and form of this technological flow.
Specially designed or prepared storage containers or containers are used in the irradiated fuel reprocessing plant. These containers or containers shall be resistant to corrosion by nitric acid. They are usually made of materials such as low-carbon stainless steel, titanium or 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:
(1) walls or internal structures corresponding to at least 2% boron equivalent; or
(2) maximum diameter 175 mm for cylindrical containers; or
(3) a maximum width of 75 mm for each plate or ring vessel.
4. Fuel cell plants for nuclear reactors and equipment specially designed or modified for this purpose
Note
Nuclear fuel cells are manufactured from one or more source or special fissile materials. For an oxygen-based fuel, the most common type of fuel, this refers to a device for pressing tablets, sintering, crushing and sorting. MOX fuel shall be handled in glove chambers (or similar spaces) until it is hermetically sealed in the coating. In all cases the fuel shall be hermetically sealed inside a suitable coating, which shall be designed as a primary container closing the fuel so as to ensure adequate performance and safety in the operation of the reactor. In all cases, extremely high standards of accurate control of procedures, procedures and equipment are also necessary to ensure predictable and safe fuel performance.
Items corresponding to the term "equipment specially designed or modified 'for the production of fuel elements include equipment which:
(a) normally come into direct contact or process or direct the production flow of nuclear material;
(b) hermetically seal nuclear material inside the coating;
(c) check the integrity of the coating or hermetic seal; or
(d) control the final treatment of hermetically sealed fuel.
Note
Such equipment or systems may include, for example:
(1) fully automated control stents specially designed or prepared to control final dimensions and surface defects of fuel tablets;
(2) automatic welding machines specially designed or modified for the welding of fuel cell end caps (or rods);
(3) Automatic test and control stents specially designed or modified to check the integrity of finished fuel cells (or rods).
Item 3 typically includes equipment for:
(a) X-ray testing of welds of cells (or bars) and end caps;
(b) detection of helium leakage from pressure cells (or rods);
(c) gamma-scanning of cells (or bars) to verify the accuracy of their filling with fuel tablets.
5. Race for the separation of uranium isotopes and equipment, other than analytical instruments, specially designed or modified for this purpose
Items corresponding to the term "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
Note
The gas centrifuge usually consists of a thin-wall cylinder (s) with a diameter of 75 mm (3 in) to 400 mm (16 in) located in a vacuum environment and rotating at a high circumference speed, of 300 m / s or more, around a vertical axis. In order to achieve such a high speed, the design materials of the rotary components shall have a high strength relative to the mass. The assembly unit of the rotor and therefore its individual components must be produced with very small tolerances to reduce the imbalance of operation. Unlike other centrifuges, the uranium enrichment gas centrifuge is characterised by a rotor chamber with a rotating disc deflector (s) and a stationary tube assembly for the supply and collection 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. The vacuum also contains a number of critical parts that do not rotate and which, although specially designed, are not difficult to produce and which are not made from special materials. However, gas centrifuge devices require a large number of these components, so their amount can provide important guidance on end-use.
5.1.1. Rotary components
(a) Complete rotor assemblies
Thin-wall cylinders, or a series of interconnected thin-wall cylinders, which are made from one of the materials having a high strength to density ratio, as described in the note to this paragraph. If the cylinders are connected, the connections are obtained by flexible bellows or rings as described in paragraph 5.1.1. (c). The rotor is equipped with an internal deflector (s) and the end caps described in paragraphs 5.1.1 (d) and 5.1.1 (e). However, the complete assembly can only be supplied partially assembled.
(b) Rotor tubes
Specially designed or modified thin-wall cylinders with a wall thickness of 12 mm (0,5 in) or less, of a diameter of 75 mm (3 in) to 400 mm (16 in) made from any of the materials having a high strength to density ratio described in note to this paragraph.
(c) Rings or bellows
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 wavelength is a rolled short cylinder with a diameter of 75 mm (3 in) to 400 mm (16 in) with a maximum wall thickness of 3 mm (0,12 in) made of high strength to density ratio materials as described in the note to this paragraph.
(d) Deflectors
Circular components with a diameter of 75 mm (3 in) to 400 mm (16 in) specially designed or prepared for installation inside a rotor tube centrifuge designed to separate the sampling chamber from the main separation chamber and in some cases assist the circulation of UF6 gas within the main separation chamber of the rotor tube. They are made of one of the materials having a high strength to density ratio as described in note to this paragraph.
(e) Upper end caps
Circular components with a diameter of 75 mm (3 in) to 400 mm (16 in) 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 upper bearing (top cap) or carry the rotational parts of the engine and lower bearing (bottom cap). They are made of one of the materials having a high strength to density ratio as described in note to this paragraph.
Note
The following materials are used for rotating parts of centrifuges:
(a) high strength steel having a tensile strength of 2,05 x 103 MPa (300,000 psi) or more;
(b) aluminium alloys having a tensile strength of 0,46 x 103 MPa (67 000 psi) or more;
(c) fibrous materials, suitable for use in composite structures, having a specific modulus equal to or greater than 12,3 x 106 m and a specific limit tensile strength equal to or greater than 0,3 x 106 m ("specific modulus" is Yang module in N / m2 divided by the specific weight in N / m3; "specific tensile strength limit" is the tensile strength limit in N / m2 divided by the specific weight in N / m3).
5.1.2. Non-moving components
(a) Magnetic suspension bearings
Specially designed or prepared bearing assemblies consisting of ring magnets suspended inside a housing containing a buffer medium. The housing is made of material resistant to UF6 (see Note to paragraph 5.2). Magnetic pairs with pole attachments or second magnet are connected to the top cap described in paragraph 5.1.1. (e). The magnet can be ring shaped, with the maximum ratio between the outer diameter and the inner diameter equal to 1.6: 1. The magnet may have an initial permeability of at least 0,15 H / m (120,000 in CGS units), a minimum remanence of 98,5% or more and an energy yield of more than 80 kJ / m3 (107 Gauss-oersteds). In addition to the usual material characteristics, it is necessary that the deviation of the magnetic axis from the geometric axis is limited by very small tolerances (less than 0,1 mm) or that a specific requirement for the homogeneity of the magnet material is applied.
(b) Bearings / dampers
Specially designed or modified bearings incorporating a pivot / cap assembly mounted on a shock absorber. The swivel pin is usually a hardened steel shaft with a hemisphere at one end and a fixture for the lower cap, as described in paragraph 5.1.1 (e), at the end of the second. A hydrodynamic bearing can be connected to the shaft. The lid is a pellet with a semi-spherical socket on one of the surfaces. These components are often supplied separately from the silencer.
(c) Molecular pumps
Specially designed or prepared cylinders having internal machined or extruded helical grooves and internal machined openings. Typical dimensions are as follows: internal diameter 75 mm (3 in) to 400 mm (16 in), wall thickness at least 10 mm (0,4 in), with a length to diameter ratio of 1: 1 or more. The tracks have a typical rectangular cross-section and depth of 2 mm (0,08 in) or greater.
(d) Engine stators
Specially designed or modified ring stators for high-speed multi-phase alternating hysteresis (or Reluctant) motors modified for synchronous operation in vacuum in the 600-2000 Hz frequency range and 50-1000 VA power range. The stators consist of multi-phase winding on a laminated iron core with small losses, consisting of thin iron sheets usually of a thickness of 2 mm (0,08 in) or less.
(e) 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 (1,2 in) 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 st. The housing can also be of a honeycomb type for storing several rotor tubes. The cases are made of or protected by materials resistant to corrosion by UF6.
(f) Shoulders
Pipes with an internal diameter of up to 12 mm, specially designed or prepared for the extraction of UF6 gas from a rotor tube based on the effect of the 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. The pipes are made of or protected by corrosion resistant materials of UF6.
5.2. Auxiliary systems, equipment and components specially designed or modified for enrichment plants with gas centrifuges
Note
Auxiliary systems, equipment and components for enrichment plants with gas centrifuges are systems ensuring the introduction of UF6 into centrifuges and the connection of individual centrifuges into cascades (or stages), which allows a gradual increase in enrichment and removal of "product" and "residue" UF6 from centrifuges, together with the equipment needed for centrifuge propulsion or plant control. The UF6 is usually evaporated from a solid phase in heated autoclaves and then distributed in gaseous form into centrifuges through the cascade collector (s) pipe. "Product" and "remnants" of UF6 gas flowing from centrifuges also pass through the cascade collector (s) tubes to freezing separators operating at 203 K (-70 ° C), where they condense and are then transferred to containers suitable for transport or storage. Since the enrichment plant consists of many thousands of centrifuges arranged in cascades, it contains many kilometres of pipe systems of cascade collectors (collectors) involving thousands of welds with many repetitive arrangements. Equipment, components and pipe systems are designed to meet the requirements of very high vacuum and purity standards.
5.2.1. Power systems / systems for product and residue extraction
Specially designed or modified technological systems include:
(a) power-operated autoclaves (or stations) used to bring UF6 into centrifugal cascades at pressures up to 100 kPa (15 psi) and flows of 1 kg / h or greater;
(b) desublimators (or freezing precipitators) used to remove UF6 from cascades at pressures up to 3 kPa (0,5 psi) (desublimators may be cooled to 203 K (-70 ° C) and heated to 343 K (+ 70 ° C);
(c) "product" and "residues" stations used to fill UF6 into containers.
This plant, equipment and piping are fully made of corrosion resistant materials of UF6 or such materials lined (see Note to paragraph 5.2) and manufactured to meet the requirements of very high vacuum and purity standards.
5.2.2. Machine piping systems for collectors
Specially designed or modified piping and collector systems 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 (s). This arrangement is repeated many times. All of these systems are made of corrosion resistant materials of UF6 (see Note to paragraph 5.2) and manufactured to meet the requirements of very high vacuum and purity standards.
5.2.3. Mass spectrometers for UF6 analysis / ion source
a.
(1) unit resolution capacity for atomic mass exceeding 320;
(2) ion sources manufactured from, or coated with, nichrome, monel or nickel;
(3) ion sources with electron bombardment ionisation;
(4) Collector system suitable for isotopic analysis.
5.2.4. Frequency changers
Frequency changers (also known as converters or inverters) specially designed or modified for the supply of engine stators as defined in paragraph 5.1.2. (d) or parts, components and assembly subsystems of such frequency converters, having all of the following:
(1) multi-phase output in the 600-2000 Hz frequency area;
(2) high stability (with a frequency control better than 0,1%);
(3) low harmonic distortion (less than 2%); and
(4) Efficacy greater than 80%.
Note
The above items either come into direct contact with UF6 gas in the technological process or directly regulate centrifuges and gas flow from centrifuge to centrifuge and cascade. corrosion resistant materials of UF6 include stainless steel, aluminium, aluminium alloys, nickel or nickel alloys containing at least 60% nickel.
5.3. Specially designed or prepared assemblies and components for use in gas diffusion enrichment
Note
In the gas diffusion separation method, the main technological equipment consists of special porous barriers for gas diffusion, heat exchangers for cooling gas (which is heated during compression), closing and regulating valves and piping networks. As the gas diffusion technology is based on the use of uranium hexafluoride (UF6), all surfaces of equipment, pipes and apparatus (which come into contact with gas) must be made of materials which remain stable in contact with UF6. The gas diffusion plant requires a large number of these units so that the quantity can be an important indication of end-use.
5.3.1. Gas diffusion bulkheads
(a) specially designed or prepared thin porous filters with a pore size of between 100 and 1000 nm (angström), a thickness of 5 mm (0,2 in) or less and a tubular shape of 25 mm (1 in) or less, made of metallic, polymer or ceramic materials resistant to corrosion by UF6;
(b) specially prepared compounds or powders for the manufacture of such filters. Such compounds and powders contain nickel or nickel alloys with a minimum nickel content of 60%, aluminium oxide or to UF6 fully resistant fluorinated hydrocarbon polymers with a purity of 99,9% or more, with a particle size of less than 10- 5 m and a high particle size uniformity which are specially designed for the production of gas diffusion bulkheads.
5.3.2. Diffuser lockers
a. These containers are made or internally lined with corrosion resistant materials of UF6 and designed for installation in horizontal or vertical positions.
5.3.3. Compressors and gas blowers
Specially designed or prepared axial, centrifugal or volume compressors or gas blowers with a minimum suction capacity of 1 m3 / min UF6 and a discharge pressure of up to several hundred kPa (100 psi) designed for long-term work in UF6 with or without an electric motor of adequate power, as well as individual assemblies of such compressors and blowers. These compressors and blowers have a pressure ratio of 2: 1 to 6: 1 and are made of or coated with materials resistant to corrosion by UF6.
5.3.4. shaft sealing
a. Such seals are usually designed for a balancing gas penetration rate of less than 1000 cm3 / min (60 in3 / min).
5.3.5. Heat exchangers for UF6 cooling
Specially designed or prepared heat exchangers made of or coated with materials resistant to corrosion by UF6 (excluding stainless steel) or copper. They are designed for a maximum pressure change rate due to leakage of less than 10 Pa (0,0015 psi) per hour at a pressure difference of 100 kPa (15 psi).
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Regulation Information
| Citation | Decree of the State Office for Nuclear Safety No. 179 / 2002 Coll., establishing a list of selected items and dual-use items in the nuclear field |
|---|---|
| Regulation Type | Order |
| Author | - |
| Collection | Code of Laws |
| Date of Promulgation | 09.05.2002 |
|---|---|
| Effective from | 01.06.2002 |
| Effective until | - |
| Status | Valid |
The regulation text is for informational purposes only.
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