CATEGORY 0 - NUCLEAR MATERIALS, FACILITIES AND EQUIPMENT
0 A - Equipment, assemblies and components
0A001 - “Nuclear reactors” and their specially designed or prepared equipment and components:
b. | metal vessels, or their main prefabricated elements, including the cover of the reactor pressure vessel, specially designed or prepared to contain the core of a “nuclear reactor”; |
vs. | handling equipment specially designed or prepared for introducing or extracting fuel from a “nuclear reactor”; |
d. | control rods specially designed or prepared for regulating the fission process in a "nuclear reactor", their support or suspension structures, the control rod adjustment mechanisms and the guide tubes of such rods; |
e. | pressure tubes specially designed or prepared to contain fuel elements and primary coolant in a “nuclear reactor”. |
f. | metallic zirconium tubes or zirconium-based alloy tubes (or tube assemblies) specially designed or prepared for use as fuel cladding in a “nuclear reactor”, in quantities exceeding 10 kg;
NB: |
For zirconium pressure tubes see paragraph 0A001.e., and for vessel tubes see paragraph 0A001.h. |
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g. | cooling pumps or accelerators specially designed or prepared for circulating the primary cooling fluid of “nuclear reactors”; |
h. | 'nuclear reactor internals' specially designed or prepared for use in a 'nuclear reactor', including core support columns, fuel channels, reactor tubes, heat shields, baffles, plates with heart grille and diffuser plates; Technical note: In paragraph 0A001.h., the expression 'internals of a nuclear reactor' means any major structure located inside a reactor vessel and fulfilling one or more of the following functions: supporting the core, maintaining fuel alignment, primary coolant guidance, shielding of the reactor vessel against radiation and adjustment of core instruments. |
i. | heat exchangers:
1. | steam generators specially designed or prepared for the primary or intermediate cooling fluid circuit of a “nuclear reactor”; |
2. | other heat exchangers specially designed or prepared for use in the primary coolant circuit of a “nuclear reactor”; |
Note: |
Paragraph 0A001.i. does not control heat exchangers intended for reactor auxiliary systems, for example the emergency cooling system or the decay heat removal cooling system. |
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j. | neutron detectors specially designed or prepared to determine neutron flux levels in the core of a “nuclear reactor”; |
k. | 'External heat shields' specially designed or prepared for use in a 'nuclear reactor' to reduce heat loss and provide protection to the containment vessel. Technical note: In 0A001.k., 'external heat shields' means any major structure placed above the reactor vessel and intended to reduce heat loss from the reactor and the temperature in the containment vessel. |
0 B - Testing, inspection and production equipment
0B001 - Facilities for separating isotopes of “natural uranium”, “depleted uranium” and “special fissile materials”, as well as equipment and components specially designed or prepared therefor, as follows:
a. | installations specially designed for the separation of isotopes of “natural uranium”, “depleted uranium” or “special fissile materials”, as follows:
1. | gas centrifuge separation installations; |
2. | gas diffusion separation installations; |
3. | aerodynamic separation installations; |
4. | chemical exchange separation installations; |
5. | ion exchange separation installations; |
6. | installations for separating isotopes by “laser” on atomic vapor; |
7. | installations for separating isotopes by “laser” irradiation of molecules; |
8. | plasma separation installations; |
9. | electromagnetic separation installations; |
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b. | gas centrifuges and assemblies and components, specially designed or prepared for the gas centrifuge separation process, as follows: Technical note: In 0B001.b., 'material having a high strength-to-density ratio' means one of the following materials:
1. | maraging steel having a maximum tensile strength equal to or greater than 1.95 GPa; |
2. | aluminum alloys having a maximum tensile strength equal to or greater than 0.46 GPa; Or |
3. | “fibrous or filamentary materials” having a “specific modulus” greater than 3.18 × 10 6 m and a “specific tensile strength” greater than 7.62 × 10 4 m; |
2. | complete rotor assemblies; |
3. | cylinders rotor tubes with a thickness of 12 mm or less, with a diameter between 75 and 650 mm, made of 'materials with a high strength-to-density ratio'; |
4. | rings or bellows with a wall thickness of 3 mm or less and a diameter between 75 and 650 mm, intended to locally support a rotor tube or to assemble a number of rotor tubes, made of 'materials having a high strength-to-density ratio'; |
5. | baffles with a diameter between 75 and 650 mm intended to be mounted inside a rotor tube, made of 'materials having a high strength-to-density ratio'; |
6. | top or bottom covers with a diameter between 75 and 650 mm designed to fit the ends of a rotor tube and made of 'materials having a high strength-to-density ratio'; |
7. | Magnetic media, as follows:
a. | Bearing assemblies consisting of a ring-shaped magnet suspended within a housing made of or coated with "UF 6 corrosion resistant materials ", containing a damping fluid. The magnet is coupled to a pole piece or a second magnet attached to the upper cover of the rotor; |
b. | active magnetic bearings specially designed or prepared for use with gas centrifuges. |
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8. | specially prepared bearings consisting of a pivot-bowl assembly mounted on a shock absorber; |
9. | molecular pumps consisting of cylinders having internal machined or spun helical grooves and internally machined bores; |
10. | toroidal motor stators for multiphase alternating current hysteresis (or reluctance) motors intended to operate under vacuum synchronously at a frequency of at least 600 Hz and a power of at least 40 VA; |
11. | Centrifuge enclosures/enclosures intended to contain the tubular rotor assembly of a gas centrifuge, consisting of a rigid cylinder having a wall thickness of not more than 30 mm, having undergone precision machining at the ends which are parallel to each other and perpendicular to the longitudinal axis of the cylinder, with a maximum clearance of 0.05 degrees; |
12. | bailers made up of tubes specially designed or prepared for the extraction of the UF 6 gas contained in the bowl according to the Pitot tube principle, and which can be attached to the central gas extraction system; |
13. | frequency changers (converters or inverters) specially designed or prepared for powering motor stators for enrichment by gas centrifuges and having all of the following characteristics, as well as components specially designed for this purpose:
a. | a multi-phase frequency output of at least 600 Hz; And |
b. | high stability (with frequency control greater than 0.2%); |
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14. | shut-off and control valves as follows:
a. | shut-off valves specially designed or prepared to act on the feed, product or releases into the UF 6 gas streams of an individual gas centrifuge; |
b. | bellows, shut-off or control valves, made of or coated with “materials resistant to corrosion by UF 6 ”, with an internal diameter of between 10 mm and 160 mm, specially designed or prepared for use in main or auxiliary systems of enrichment plants using gas centrifuges; |
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vs. | equipment and components, as follows, specially designed or prepared for the gas diffusion separation process:
1. | gas diffusion barriers made of porous metallic, polymer or ceramic materials “resistant to corrosion by UF 6 ”, with a pore size of 10 to 100 mm, a thickness equal to or less than 5 mm and, for tubular configurations, with a diameter equal to or less than 25 mm; |
2. | gas diffusion boxes made of or coated with “materials resistant to corrosion by UF 6 ”; |
3. | compressors (axial, centrifugal or positive displacement) or gas blowers having a suction capacity of 1 m 3 /min or more of UF 6 , an outlet pressure of up to 500 kPa, and a pressure ratio equal to or less than 10 :1, and made of or coated with “materials resistant to corrosion by UF 6 ”; |
4. | compressor or blower shaft seals specified in 0B001.c.3. and designed for a buffer gas penetration rate of less than 1,000 cm 3 /min; |
5. | heat exchangers made of or coated with “materials resistant to corrosion by UF 6 ”, and designed for a rate of pressure loss due to leakage of less than 10 Pa per hour under a differential pressure of 100 kPa; |
6. | bellows valves, manual or automatic, shut-off or control, made of or coated with “materials resistant to corrosion by UF 6 ”; |
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d. | equipment and components specially designed or prepared for the aerodynamic separation process:
1. | separation nozzles consisting of curved slotted pipes with a radius of curvature less than 1 mm, resistant to corrosion by UF 6 (inside the nozzle there is a distribution knife which separates the flow passing through the nozzle in two streams); |
2. | cylindrical or conical tubes with flow-controlled tangential inlet channels (vortex tubes), made of or coated with “materials resistant to corrosion by UF 6 ” and provided with one or more tangential inlet channels; |
3. | gas compressors or blowers made of or coated with “materials resistant to corrosion by UF 6 ”, and corresponding bearing linings; |
4. | heat exchangers made of or coated with “materials resistant to corrosion by UF 6 ”; |
5. | enclosures for aerodynamic separation elements, made of or coated with “materials resistant to corrosion by UF 6 ”, intended to receive vortex tubes or separation nozzles; |
6. | bellows valves, manual or automatic, shut-off or control, made of or coated with “materials resistant to corrosion by UF 6 ”, with a diameter equal to or greater than 40 mm; |
7. | systems for separating UF 6 and carrier gas (hydrogen or helium) to reduce the UF 6 content to 1 ppm or less comprising the following equipment:
a. | cryogenic heat exchangers and cryoseparators capable of reaching temperatures less than or equal to 153 K (-120 °C); |
b. | cryogenic refrigeration devices capable of reaching temperatures less than or equal to 153 K (-120 °C); |
vs. | separation nozzles or vortex tubes to separate UF 6 from the carrier gas; |
d. | cold traps capable of freezing UF 6 ; |
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e. | equipment and components specially designed or prepared for the chemical exchange separation process:
1. | pulsed rapid liquid-liquid exchange columns having a residence time corresponding to one stage of 30 seconds or less and resistant to corrosion by concentrated hydrochloric acid solutions (for example made of or coated with suitable plastic materials such as polymers of 'fluorinated hydrocarbons or glass); |
2. | pulsed liquid-liquid rapid centrifugal contactors having a one-stage residence time of 30 seconds or less and resistant to corrosion by concentrated hydrochloric acid solutions (e.g. made of or coated with suitable plastic materials such as hydrocarbon polymers fluorinated or glass); |
3. | electrochemical reduction cells resistant to corrosion by concentrated hydrochloric acid solutions for the conversion of uranium by reduction from one valence state to another; |
4. | systems at the end of the electrochemical reduction cell cascade designed to sample U +4 from the organic flow and, for parts in contact with the flow, made of or coated with suitable materials (e.g. glass, polymeric fluorocarbons, sulfate polyphenyl, polyether sulfone and resin-impregnated graphite); |
5. | feed preparation systems for producing high purity uranium chloride solutions consisting of dissolution, solvent extraction and/or ion exchange purification equipment, as well as electrolytic cells for reducing uranium U + 6 or U + 4 to U + 3 ; |
6. | uranium oxidation systems to oxidize U +3 to U +4 ; |
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f. | equipment and components specially designed or prepared for the ion exchange separation process, as follows:
1. | fast reacting ion exchange resins, porous macrocrosslinked or film resins in which the active chemical exchange groups are limited to a surface coating on an inactive porous support and other composite structures in a suitable form, and in particular in the form of particles or fibers with a diameter less than or equal to 0.2 mm, resistant to concentrated hydrochloric acid and designed to obtain an exchange rate with a half-reaction time of less than 10 seconds and effective at temperatures between 373 K (100°C) and 473K (200°C); |
2. | ion exchange columns (cylindrical) larger than 1000 mm in diameter made of or lined with materials resistant to concentrated hydrochloric acid (e.g. titanium or fluorocarbon plastics) and capable of operating at temperatures between 373 K (100 °C) and 473 K (200 °C) and at pressures above 0.7 MPa; |
3. | reflux ion exchange systems (chemical or electrochemical oxidation or reduction systems) for the regeneration of chemical reduction or oxidation agents used in ion exchange enrichment cascades; |
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g. | equipment and components specially designed or prepared for laser separation processes using laser atomic vapor isotopic separation:
1. | uranium vaporization systems designed to achieve a power delivered to the target equal to or greater than 1 kW for use in connection with laser enrichment; |
2. | liquid or vaporized uranium metal handling systems specially designed or prepared for handling molten uranium, molten uranium alloys or vaporized uranium metal, for use in connection with laser enrichment, and their components specially designed;
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3. | manifold assemblies for products and rejects for liquid or vaporized uranium metal, made of or coated with materials resistant to heat and corrosion by vaporized or liquid uranium metal such as tantalum or oxide-coated graphite 'yttrium; |
4. | separator module enclosures (cylindrical or rectangular containers) to house the uranium metal vapor source, the electron gun and the product and residue collectors; |
5. | “lasers” or “laser” systems specially designed or prepared for the separation of uranium isotopes provided with a frequency stabilizer to be able to operate for long periods;
NB: |
SEE ALSO 6A005 AND 6A205. |
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h. | equipment and components specially designed or prepared for laser separation processes using laser molecular isotope separation:
1. | supersonic expansion nozzles for cooling mixtures of UF 6 and carrier gas to 150 K (- 123 °C) or less and made of “materials resistant to corrosion by UF 6 ”; |
2. | collecting components or devices for products or releases specially designed or prepared to collect releases of uranium and uranium-based material produced by exposure to laser light flux, consisting of “materials resistant to corrosion by UF 6 ”; |
3. | heat compressors made of or coated with “materials resistant to corrosion by UF 6 ”, and corresponding bearing linings; |
4. | equipment used for the fluorination of UF 5 (solid) into UF 6 (gas); |
5. | systems for separating UF 6 and carrier gas (for example nitrogen or argon or other gases) comprising the following equipment:
a. | cryogenic heat exchangers and cryoseparators capable of reaching temperatures less than or equal to 153 K (-120 °C); |
b. | cryogenic refrigeration devices capable of reaching temperatures less than or equal to 153 K (-120 °C); |
d. | cold traps capable of freezing UF 6 ; |
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6. | “lasers” or “laser” systems specially designed or prepared for the separation of uranium isotopes provided with a frequency stabilizer to be able to operate for long periods;
NB: |
SEE ALSO 6A005 AND 6A205. |
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i. | equipment and components specially designed or prepared for the plasma separation process:
1. | microwave energy sources and antennas for producing or accelerating ions and having the following characteristics: output frequency greater than 30 GHz and average output power greater than 50 kW; |
2. | high frequency ion exciter coils for frequencies above 100 kHz and capable of supporting an average power above 40 kW; |
3. | uranium plasma generator systems; |
5. | collector assemblies for products and rejects for uranium metal in solid form, made of or coated with materials resistant to heat and corrosion by vaporized or liquid uranium such as tantalum or graphite coated with oxide yttrium; |
6. | separator module enclosures (cylindrical) intended to house the uranium plasma source, the high frequency exciter coil and the product and residue collectors, and made of a suitable non-magnetic material (e.g. stainless steel); |
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j. | equipment and components, specially designed or prepared for the electromagnetic separation process, as follows:
1. | single or multiple ion sources, including the vapor source, ionizer and beam accelerator, made of suitable non-magnetic materials (e.g. graphite, stainless steel or copper) and capable of providing full ionization current equal to or greater than 50 mA; |
2. | ion collecting plates having slots or pockets (two or more) for collecting beams of enriched or depleted uranium ions, and made of suitable non-magnetic materials (e.g. graphite or stainless steel); |
3. | vacuum chambers for electromagnetic uranium separators, made of non-magnetic materials (e.g. stainless steel) and designed to operate at pressures of 0.1 Pa or less; |
4. | pole pieces with a diameter of more than 2 m; |
5. | high voltage power supplies for ion sources having all of the following characteristics:
a. | capable of permanent operation; |
b. | output voltage greater than or equal to 20,000 V; |
vs. | output current greater than or equal to 1A; And |
d. | voltage regulation better than 0.01% over an 8 hour period; |
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6. | magnet power supplies (high current, direct current) having all of the following characteristics:
a. | capable of continuous operation with an output current greater than or equal to 500 A at a voltage greater than or equal to 100 V; And |
b. | current or voltage regulation better than 0.01% over an 8 hour period. |
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0B002 - Auxiliary systems, equipment and components specially designed or prepared, for isotope separation plants specified in paragraph 0B001, made of or coated with "materials resistant to corrosion by UF 6 ":
a. | feed autoclaves, furnaces or systems, used to introduce UF 6 into the enrichment system; |
b. | condensers or cold traps used to extract UF 6 from the enrichment system for transfer by reheat; |
vs. | product and residue stations for transferring UF 6 into containers; |
d. | liquefaction or solidification stations used to extract UF 6 from the enrichment system by compression, cooling and conversion of UF 6 into liquid or solid form; |
e. | pipes and collectors specially designed for handling UF 6 inside diffusion, centrifugation or aerodynamic cascades; |
f. | vacuum systems and pumps:
1. | vacuum distributors, vacuum collectors or vacuum pumps having a suction capacity equal to or greater than 5 m 3 /minute; Or |
2. | vacuum pumps specially designed to operate in a UF 6 atmosphere ; made of or coated with “materials resistant to corrosion by UF 6 ”; Or |
3. | Vacuum installations consisting of vacuum distributors, vacuum collectors or vacuum pumps, and designed to operate in a UF 6 atmosphere ; |
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g. | UF 6 mass spectrometers /ion sources capable of taking samples online from UF 6 gas streams and having all of the following characteristics:
1. | capable of measuring ions of 320 atomic mass units or greater, and having a resolution better than 1 part in 320: |
2. | ion sources made of or coated with nickel, nickel-copper alloy containing at least 60% nickel by weight, or nickel-chromium alloys; |
3. | electron bombardment ionization sources; And |
4. | having a collector system suitable for isotopic analysis. |
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0B003 - Uranium conversion plants and specially designed or prepared equipment:
a. | systems for converting uranium ore concentrates into UO 3 ; |
b. | systems for the conversion of UO 3 to UF 6 ; |
vs. | systems for converting UO 3 to UO 2 ; |
d. | systems for the conversion of UO 2 to UF 4 ; |
e. | systems for the conversion of UF 4 to UF 6 ; |
f. | systems for the conversion of UF 4 to uranium metal; |
g. | systems for the conversion of UF 6 to UO 2 ; |
h. | systems for converting UF 6 to UF 4 ; |
i. | systems for the conversion of UO 2 to UCl 4 . |
0B004 - installations for the production or concentration of heavy water, deuterium or deuterium compounds, and specially designed or prepared equipment and components:
a. | installations for the production of heavy water, deuterium or deuterium compounds, as follows:
1. | water-hydrogen sulphide exchange installations; |
2. | ammonia-hydrogen exchange installations; |
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b. | equipment and components, as follows:
1. | water-hydrogen sulfide exchange towers with a diameter of 1.5 m or more, capable of operating at pressures of 2 MPa or more; |
2. | single-stage centrifugal blowers or compressors under low pressure (i.e. 0.2 MPa) for the circulation of hydrogen sulfide (i.e. a gas containing more than 70% H 2 S ) with a flow capacity greater than or equal to 56 m 3 /s when operating at suction pressures greater than or equal to 1.8 MPa and are equipped with seals designed for use in humid environments in the presence of H 2 S; |
3. | ammonia-hydrogen exchange towers with a height greater than or equal to 35 m, having a diameter between 1.5 and 2.5 m and capable of operating at pressures greater than 15 MPa; |
4. | tower internals, including stage contactors, and stage pumps, including submersible pumps, for the production of heavy water by the ammonia-hydrogen exchange process; |
5. | ammonia crackers having an operating pressure greater than or equal to 3 MPa for the production of heavy water by the ammonia-hydrogen exchange process; |
6. | infrared absorption analyzers capable of analyzing the hydrogen deuterium ratio continuously with deuterium concentrations equal to or greater than 90%; |
7. | catalytic burners for the conversion of deuterium enriched by the ammonia-hydrogen exchange process into heavy water; |
8. | complete heavy water enrichment systems, or purpose-built columns, for the enrichment of heavy water to the deuterium concentration level required for reactors. |
9. | ammonia synthesis converters or ammonia synthesis units specially designed or prepared for the production of heavy water by the ammonia-hydrogen exchange process. |
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0B005 - Facilities specially designed for the manufacture of fuel elements for “nuclear reactors” and equipment specially designed or prepared for this purpose.
Technical note:
Equipment specially designed or prepared for the manufacture of fuel elements for “nuclear reactors” includes equipment which:
1. | normally comes into direct contact with, directly processes or regulates the production flow of nuclear materials; |
2. | ensures the sealing of nuclear materials inside the sheath; |
3. | checks the integrity of the sheath or seal; |
4. | verifies the finishing treatment of sealed fuel; Or |
5. | is used to assemble the reactor elements. |
0B006 - Installations for reprocessing irradiated fuel elements for “nuclear reactors” and equipment and components specially designed or prepared for this purpose .
Note: |
Paragraph 0B006 includes:
a. | irradiated nuclear fuel element reprocessing facilities, including equipment and components which are normally in direct contact with the irradiated fuel and which directly control the most important processing flows of nuclear materials and fission products; |
b. | fuel element chopping or shredding machines, i.e. remotely controlled equipment intended to cut, chop or shear irradiated nuclear fuel assemblies, bundles or rods; |
vs. | dissolvers, anti-criticality safety containers (e.g. small diameter, annular or flat containers) specially designed or prepared for the dissolution of spent nuclear fuel, capable of withstanding hot and highly corrosive liquids and capable of being charged and maintained remotely ; |
d. | solvent extractors, such as charged or pulsed columns, mixer-settlers or centrifugal contactors, resistant to the corrosive effects of nitric acid, and specially designed or prepared for use in a "natural uranium" reprocessing installation, “depleted uranium” or “special fissile material”; |
e. | storage or storage tanks specially designed to avoid criticality or to resist the corrosive action of nitric acid; Technical note:
Storage or storage tanks may have the following characteristics:
1. | internal walls or structures having a boron equivalent (calculated for all constituents as defined in the note to paragraph 0C004) of at least 2%; |
2. | a maximum diameter of 175 mm for cylindrical configurations; Or |
3. | a maximum width of 75 mm for a flat or annular configuration. |
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f. | neutron measurement systems specially designed or prepared for integration and use of automated process control systems in a “natural uranium”, “depleted uranium” or “special fissile material” reprocessing facility. |
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0B007 - Plutonium conversion installations and equipment specially designed or prepared therefor, as follows:
a. | plutonium nitrate to plutonium oxide conversion systems; |
b. | plutonium metal production systems. |
0C - Materials
0C001 - “Natural uranium” or “depleted uranium” or thorium in the form of a metal, an alloy, a chemical compound or a concentrate and any other material containing one or more of the above substances.
Note: |
Paragraph 0C001 does not control:
a. | charges of four grams or less of “natural uranium” or “depleted uranium” when contained in a detecting component of an instrument; |
b. | “depleted uranium” specially manufactured for the following civil non-nuclear applications:
3. | ballast with a maximum mass of 100 kg; |
4. | counterweight with a maximum mass of 100 kg; |
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vs. | alloys containing less than 5% thorium; |
d. | ceramic products containing thorium, which were manufactured for non-nuclear uses. |
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0C002 - “Special fissile materials”
Note: |
Paragraph 0C002 does not control charges of four "effective grams" or less when contained in a sensing component of an instrument. |
0C003 - Deuterium, heavy water (deuterium oxide) and other deuterium compounds as well as mixtures and solutions containing deuterium, in which the deuterium/hydrogen isotopic ratio is greater than 1/5,000
0C004 - Graphite having a purity of less than 5 parts per million boron equivalent and a density greater than 1.50 g/cm 3 for use in a “nuclear reactor”, in quantities exceeding 1 kg .
Note 1: |
For the purposes of controlling exports, the competent authorities of the Member State where the exporter is established will determine whether exports of graphite meeting the above specifications are intended for "use in a nuclear reactor" or not. |
Note 2: |
In paragraph 0C004, 'boron equivalent' (EB) is defined as the total of EB Z for impurities (excluding EB carbon since carbon is not considered an impurity), including boron , Or:
| EB Z (ppm) = FC × concentration of element Z in ppm; 
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| and where s B and s Z are the thermal neutron capture sections expressed (in barns) respectively for boron present in nature and the element Z, A B and A Z being the atomic masses of boron present in nature and of element Z, respectively. |
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0C005 - Compounds or powders specially prepared for the formation of gas diffusion barriers, resistant to corrosion by UF 6 (for example nickel or an alloy containing 60% by weight or more of nickel, aluminum oxide and fully fluorinated hydrocarbon polymers), having a degree of purity of 99.9% by weight or greater, an average particle size of less than 10 micrometers - measured according to ASTM B330 - and a high degree of uniformity of particle dimensions.
0D - Software
0D001 - “Software” specially designed or modified for the “development”, “production” or “use” of goods included in this category.
0E - Technology
0E001 - “Technology”, within the meaning of the Nuclear Technology Note, for the “development”, “production” or “use” of goods included in this category.
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