The corresponding systems, equipment and components as identified in Council Regulation (EC) No 428/2009 of 5 May 2009 setting up a Community regime for the control of exports, transfer, brokering and transit of dual-use items Nuclear Suppliers Group's control list as in INFCIRC/254/Rev.12/Part 1 (1)

0A001 “Nuclear reactors” and specially designed or prepared equipment and components therefor, as follows: TLB1.1 Complete nuclear reactors

0A001.a “Nuclear reactors”; TLB1.1 Nuclear reactors capable of operation so as to maintain a controlled self-sustaining fission chain reaction. EXPLANATORY NOTE A “nuclear reactor” basically includes the items within or attached directly to the reactor vessel, the equipment which controls the level of power in the core, and the components which normally contain or come in direct contact with or control the primary coolant of the reactor core. EXPORTS The export of the whole set of major items within this boundary will take place only in accordance with the procedures of the Guidelines. Those individual items within this functionally defined boundary which will be exported only in accordance with the procedures of the Guidelines are listed in paragraphs 1.2. to 1.11. The Government reserves to itself the right to apply the procedures of the Guidelines to other items within the functionally defined boundary

0A001.b Metal vessels, or major shop-fabricated parts therefor, including the reactor vessel head for a reactor pressure vessel, specially designed or prepared to contain the core of a “nuclear reactor”; TLB1.2 Nuclear reactor vessels Metal vessels, or major shop-fabricated parts therefor, especially designed or prepared to contain the core of a nuclear reactor as defined in paragraph 1.1. above, as well as relevant reactor internals as defined in paragraph 1.8. below. EXPLANATORY NOTE Item 1.2 covers nuclear reactor vessels regardless of pressure rating and includes reactor pressure vessels and calandrias. The reactor vessel head is covered by item 1.2. as a major shop-fabricated part of a reactor vessel.

0A001.c Manipulative equipment specially designed or prepared for inserting or removing fuel in a “nuclear reactor”; TLB1.3 Nuclear reactor fuel charging and discharging machines Manipulative equipment especially designed or prepared for inserting or removing fuel in a nuclear reactor as defined in paragraph 1.1. above. EXPLANATORY NOTE The items noted above are capable of on-load operation or at employing technically sophisticated positioning or alignment features to allow complex off-load fueling operations such as those in which direct viewing of or access to the fuel is not normally available.

0A001.d Control rods specially designed or prepared for the control of the fission process in a “nuclear reactor”, support or suspension structures therefor, rod drive mechanisms and rod guide tubes; TLB1.4 Nuclear reactor control rods and equipment Especially designed or prepared rods, support or suspension structures therefor, rod drive mechanisms or rod guide tubes to control the fission process in a nuclear reactor as defined in paragraph 1.1. above.

0A001.e Pressure tubes specially designed or prepared to contain both fuel elements and the primary coolant in a “nuclear reactor”; TLB1.5 Nuclear reactor pressure tubes Tubes which are especially designed or prepared to contain both fuel elements and the primary coolant in a reactor as defined in paragraph 1.1. above. EXPLANATORY NOTE Pressure tubes are parts of fuel channels designed to operate at elevated pressure, sometimes in excess of 5 MPa.

0A001.f Zirconium metal tubes or zirconium alloy tubes (or assembles of tubes) specially designed or prepared for use as fuel cladding in a “nuclear reactor”, and in quantities exceeding 10 kg; N.B.: For zirconium pressure tubes see 0A001.e. and for calandria tubes see 0A001.h. TLB1.6 Nuclear fuel cladding Zirconium metal tubes or zirconium alloy tubes (or assemblies of tubes) especially designed or prepared for use as fuel cladding in a reactor as defined in paragraph 1.1. above, and in quantities exceeding 10 kg. N.B.: For zirconium pressure tubes see 1.5. For calandria tubes see 1.8. EXPLANATORY NOTE Zirconium metal tubes or zirconium alloy tubes for use in a nuclear reactor consist of zirconium in which the relation of hafnium to zirconium is typically less than 1:500 parts by weight

0A001.g Coolant pumps or circulators specially designed or prepared for circulating the primary coolant of “nuclear reactors”; TLB1.7 Primary coolant pumps or circulators Pumps or circulators especially designed or prepared for circulating the primary coolant for nuclear reactors as defined in paragraph 1.1. above. EXPLANATORY NOTE: Especially designed or prepared pumps or circulators include pumps for water-cooled reactors, circulators for gas-cooled reactors, and electromagnetic and mechanical pumps for liquid-metal-cooled reactors. This equipment may include pumps with elaborate sealed or multi-sealed systems to prevent leakage of primary coolant, canned-driven pumps, and pumps with inertial mass systems. This definition encompasses pumps certified to Section III, Division I, Subsection NB (Class 1 components) of the American Society of Mechanical Engineers (ASME) Code, or equivalent standards.

0A001.h ‘Nuclear reactor internals’ specially designed or prepared for use in a “nuclear reactor”, including support columns for the core, fuel channels, calandria tubes, thermal shields, baffles, core grid plates, and diffuser plates; Technical Note: In 0A001.h. ‘nuclear reactor internals’ means any major structure within a reactor vessel which has one or more functions such as supporting the core, maintaining fuel alignment, directing primary coolant flow, providing radiation shields for the reactor vessel, and guiding in-core instrumentation. TLB1.8 Nuclear reactor internals “Nuclear reactor internals” especially designed or prepared for use in a nuclear reactor as defined in paragraph 1.1 above. This includes, for example, support columns for the core, fuel channels, calandria tubes, thermal shields, baffles, core grid plates, and diffuser plates. EXPLANATORY NOTE “Nuclear reactor internals” are major structures within a reactor vessel which have one or more functions such as supporting the core, maintaining fuel alignment, directing primary coolant flow, providing radiation shields for the reactor vessel, and guiding in-core instrumentation.

0A001.i Heat exchangers as follows: 1. Steam generators specially designed or prepared for the primary, or intermediate, coolant 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: 0A001.i. does not control heat exchangers for the supporting systems of the reactor, e.g., the emergency cooling system or the decay heat cooling system. TLB1.9 Heat exchangers (a) Steam generators especially designed or prepared for the primary, or intermediate, coolant circuit of a nuclear reactor as defined in paragraph 1.1 above. (b) Other heat exchangers especially designed or prepared for use in the primary coolant circuit of a nuclear reactor as defined in paragraph 1.1 above. EXPLANATORY NOTE Steam generators are especially designed or prepared to transfer the heat generated in the reactor to the feed water for steam generation. In the case of a fast reactor for which an intermediate coolant loop is also present, the steam generator is in the intermediate circuit. In a gas-cooled reactor, a heat exchanger may be utilized to transfer heat to a secondary gas loop that drives a gas turbine. The scope of control for this entry does not include heat exchangers for the supporting systems of the reactor, e.g., the emergency cooling system or the decay heat cooling system.

0A001.j Neutron detectors specially designed or prepared for determining neutron flux levels within the core of a “nuclear reactor”; TLB1.10 Neutron detectors Especially designed or prepared neutron detectors for determining neutron flux levels within the core of a reactor as defined in paragraph 1.1. above. EXPLANATORY NOTE The scope of this entry encompasses in-core and ex-core detectors which measure flux levels in a large range, typically from 104 neutrons per cm2 per second to 1010 neutrons per cm2 per second or more. Ex-core refers to those instruments outside the core of a reactor as defined in paragraph 1.1. above, but located within the biological shielding.

0A001.k ‘External thermal shields’ specially designed or prepared for use in a “nuclear reactor” for the reduction of heat loss and also for the containment vessel protection. Technical Note: In 0A001.k. ‘external thermal shields’ means major structures placed over the reactor vessel which reduce heat loss from the reactor and reduce temperature within the containment vessel. TLB1.11 External thermal shields “External thermal shields” especially designed or prepared for use in a nuclear reactor as defined in paragraph 1.1 for reduction of heat loss and also for containment vessel protection. EXPLANATORY NOTE “External thermal shields” are major structures placed over the reactor vessel which reduce heat loss from the reactor and reduce temperature within the containment vessel.

0B001 Plant for the separation of isotopes of “natural uranium”, “depleted uranium” or “special fissile materials”, and specially designed or prepared equipment and components therefor, as follows: TLB5 Plants for the separation of isotopes of natural uranium, depleted uranium or special fissionable material and equipment, other than analytical instruments, especially designed or prepared therefor

0B001.a Plant specially designed for separating isotopes of “natural uranium”, “depleted uranium”, or “special fissile materials”, as follows: 1. Gas centrifuge separation plant; 2. Gaseous diffusion separation plant; 3. Aerodynamic separation plant; 4. Chemical exchange separation plant; 5. Ion-exchange separation plant; 6. Atomic vapour “laser” isotope separation plant; 7. Molecular “laser” isotope separation plant; 8. Plasma separation plant; 9. Electro magnetic separation plant; TLB5

0B001.b Gas centrifuges and assemblies and components, specially designed or prepared for gas centrifuge separation process, as follows: Technical Note: In 0B001.b. ‘high strength-to-density ratio material’ means any of the following: 1. Maraging steel capable of an ultimate tensile strength of 1,95 GPa or more; 2. Aluminium alloys capable of an ultimate tensile strength of 0,46 GPa or more; or 3. “Fibrous or filamentary materials” with a “specific modulus” of more than 3,18 × 106 m and a “specific tensile strength” greater than 7,62 × 104 m; 1. Gas centrifuges; TLB5.1 5.1. Gas centrifuges and assemblies and components especially designed or prepared for use in gas centrifuges INTRODUCTORY NOTE The gas centrifuge normally consists of a thin-walled cylinder(s) of between 75 mm and 650 mm diameter contained in a vacuum environment and spun at high peripheral speed of the order of 300 m/s or more with its central axis vertical. In order to achieve high speed the materials of construction for the rotating components have to be of a high strength to density ratio and the rotor assembly, and hence its individual components, have to be manufactured to very close tolerances in order to minimize the unbalance. In contrast to other centrifuges, the gas centrifuge for uranium enrichment is characterized by having within the rotor chamber a rotating disc-shaped baffle(s) and a stationary tube arrangement for feeding and extracting the UF6 gas and featuring at least three separate channels, of which two are connected to scoops extending from the rotor axis towards the periphery of the rotor chamber. Also contained within the vacuum environment are a number of critical items which do not rotate and which although they are especially designed are not difficult to fabricate nor are they fabricated out of unique materials. A centrifuge facility however requires a large number of these components, so that quantities can provide an important indication of end use.

0B001.b TLB5.1.1 Rotating components

0B001.b. 2. Complete rotor assemblies; TLB5.1.1a (a) Complete rotor assemblies: Thin-walled cylinders, or a number of interconnected thin-walled cylinders, manufactured from one or more of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section. If interconnected, the cylinders are joined together by flexible bellows or rings as described in section 5.1.1.(c) following. The rotor is fitted with an internal baffle(s) and end caps, as described in section 5.1.1.(d) and (e) following, if in final form. However the complete assembly may be delivered only partly assembled.

0B001.b. 3. Rotor tube cylinders with a wall thickness of 12 mm or less, a diameter of between 75 mm and 650 mm, made from ‘high strength-to-density ratio materials’; TLB5.1.1b (b) Rotor tubes: Especially designed or prepared thin-walled cylinders with thickness of 12 mm or less, a diameter of between 75 mm and 650 mm, and manufactured from one or more of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section.

0B001.b. 4. Rings or bellows with a wall thickness of 3 mm or less and a diameter of between 75 mm and 650 mm and designed to give local support to a rotor tube or to join a number together, made from ‘high strength-to-density ratio materials’; TLB5.1.1c (c) Rings or Bellows: Components especially designed or prepared to give localized support to the rotor tube or to join together a number of rotor tubes. The bellows is a short cylinder of wall thickness 3 mm or less, a diameter of between 75 mm and 650 mm, having a convolute, and manufactured from one of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section.

0B001.b. 5. Baffles of between 75 mm and 650 mm diameter for mounting inside a rotor tube, made from ‘high strength-to-density ratio materials’. TLB5.1.1d (d) Baffles: Disc-shaped components of between 75 mm and 650 mm diameter especially designed or prepared to be mounted inside the centrifuge rotor tube, in order to isolate the take-off chamber from the main separation chamber and, in some cases, to assist the UF6 gas circulation within the main separation chamber of the rotor tube, and manufactured from one of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section.

0B001.b. 6. Top or bottom caps of between 75 mm and 650 mm diameter to fit the ends of a rotor tube, made from ‘high strength-to-density ratio materials’; TLB5.1.1e (e) Top caps/Bottom caps: Disc-shaped components of between 75 mm and 650 mm diameter especially designed or prepared to fit to the ends of the rotor tube, and so contain the UF6 within the rotor tube, and in some cases to support, retain or contain as an integrated part an element of the upper bearing (top cap) or to carry the rotating elements of the motor and lower bearing (bottom cap), and manufactured from one of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section.

TLB5.1.1 EXPLANATORY NOTE The materials used for centrifuge rotating components include the following: (a) Maraging steel capable of an ultimate tensile strength of 1,95 GPa or more; (b) Aluminium alloys capable of an ultimate tensile strength of 0,46 GPa or more; (c) Filamentary materials suitable for use in composite structures and having a specific modulus of 3,18 × 106 m or greater and a specific ultimate tensile strength of 7,62 × 104 m or greater (‘Specific Modulus’ is the Young's Modulus in N/m2 divided by the specific weight in N/m3; ‘Specific Ultimate Tensile Strength’ is the ultimate tensile strength in N/m2 divided by the specific weight in N/m3).

0B001.b TLB5.1.2 Static components

0B001.b. 7. Magnetic suspension bearings as follows: a. Bearing assemblies consisting of an annular magnet suspended within a housing made of or protected by “materials resistant to corrosion by UF6” containing a damping medium and having the magnet coupling with a pole piece or second magnet fitted to the top cap of the rotor; b. Active magnetic bearings specially designed or prepared for use with gas centrifuges. TLB5.1.2A.1 (a) Magnetic suspension bearings: 1. Especially designed or prepared bearing assemblies consisting of an annular magnet suspended within a housing containing a damping medium. The housing will be manufactured from a UF6-resistant material (see EXPLANATORY NOTE to Section 5.2.). The magnet couples with a pole piece or a second magnet fitted to the top cap described in Section 5.1.1.(e). The magnet may be ring-shaped with a relation between outer and inner diameter smaller or equal to 1,6:1. The magnet may be in a form having an initial permeability of 0,15 H/m or more, or a remanence of 98,5 % or more, or an energy product of greater than 80 kJ/m3. In addition to the usual material properties, it is a prerequisite that the deviation of the magnetic axes from the geometrical axes is limited to very small tolerances (lower than 0,1 mm) or that homogeneity of the material of the magnet is specially called for.

0B001.b. TLB5.1.2a2 2. Active magnetic bearings especially designed or prepared for use with gas centrifuges. EXPLANATORY NOTE These bearings usually have the following characteristics: — Designed to keep centred a rotor spinning at 600 Hz or more, and — Associated to a reliable electrical power supply and/or to an uninterruptible power supply (UPS) unit in order to function for more than one hour.

0B001.b. 8. Specially prepared bearings comprising a pivot-cup assembly mounted on a damper; TLB5.1.2b (b) Bearings/Dampers: Especially designed or prepared bearings comprising a pivot/cup assembly mounted on a damper. The pivot is normally a hardened steel shaft with a hemisphere at one end with a means of attachment to the bottom cap described in section 5.1.1.(e) at the other. The shaft may however have a hydrodynamic bearing attached. The cup is pellet-shaped with a hemispherical indentation in one surface. These components are often supplied separately to the damper.

0B001.b. 9. Molecular pumps comprised of cylinders having internally machined or extruded helical grooves and internally machined bores; TLB5.1.2c (c) Molecular pumps: Especially designed or prepared cylinders having internally machined or extruded helical grooves and internally machined bores. Typical dimensions are as follows: 75 mm to 650 mm internal diameter, 10 mm or more wall thickness, with the length equal to or greater than the diameter. The grooves are typically rectangular in cross-section and 2 mm or more in depth.

0B001.b. 10. Ring-shaped motor stators for multiphase AC hysteresis (or reluctance) motors for synchronous operation within a vacuum at a frequency of 600 Hz or more and a power of 40 VA or more; TLB5.1.2d (d) Motor stators: Especially designed or prepared ring-shaped stators for high speed multiphase AC hysteresis (or reluctance) motors for synchronous operation within a vacuum at a frequency of 600 Hz or greater and a power of 40 VA or greater. The stators may consist of multi-phase windings on a laminated low loss iron core comprised of thin layers typically 2,0 mm thick or less.

0B001.b. 11. Centrifuge housing/recipients to contain the rotor tube assembly of a gas centrifuge, consisting of a rigid cylinder of wall thickness up to 30 mm with precision machined ends that are parallel to each other and perpendicular to the cylinder's longitudinal axis to within 0,05 degrees or less; TLB5.1.2e (e) Centrifuge housing/recipients: Components especially designed or prepared to contain the rotor tube assembly of a gas centrifuge. The housing consists of a rigid cylinder of wall thickness up to 30 mm with precision machined ends to locate the bearings and with one or more flanges for mounting. The machined ends are parallel to each other and perpendicular to the cylinder's longitudinal axis to within 0,05 degrees or less. The housing may also be a honeycomb type structure to accommodate several rotor assemblies.

0B001.b. 12. Scoops consisting of specially designed or prepared tubes for the extraction of UF6 gas from within the rotor tube by a Pitot tube action and capable of being fixed to the central gas extraction system; TLB5.1.2f (f) Scoops: Especially designed or prepared tubes for the extraction of UF6 gas from within the rotor tube by a Pitot tube action (that is, with an aperture facing into the circumferential gas flow within the rotor tube, for example by bending the end of a radially disposed tube) and capable of being fixed to the central gas extraction system.

0B001.b. 13. Frequency changers (converters or inverters) specially designed or prepared to supply motor stators for gas centrifuge enrichment, having all of the following characteristics, and specially designed components therefor: a. A multiphase frequency output of 600 Hz or greater; and b. High stability (with frequency control better than 0,2 %); TLB5.2.5 5.2.5. Frequency changers Frequency changers (also known as converters or inverters) especially designed or prepared to supply motor stators as defined under 5.1.2.(d), or parts, components and sub-assemblies of such frequency changers having all of the following characteristics: 1. A multiphase frequency output of 600 Hz or greater; and 2. High stability (with frequency control better than 0,2 %).

0B001.b. 14. Shut-off and control valves as follows: a. Shut-off valves specially designed or prepared to act on the feed, product or tails UF6 gaseous streams of an individual gas centrifuge; b. Bellows-sealed valves, shut-off or control, made of or protected by “materials resistant to corrosion by UF6”, with an inside diameter of 10 mm to 160 mm, specially designed or prepared for use in main or auxiliary systems of gas centrifuge enrichment plants; TLB5.2.3 5.2.3 Special shut-off and control valves (a) Shut-off valves especially designed or prepared to act on the feed, product or tails UF6 gaseous streams of an individual gas centrifuge. (b) Bellows-sealed valves, manual or automated, shut-off or control, made of or protected by materials resistant to corrosion by UF6, with an inside diameter of 10 to 160 mm, especially designed or prepared for use in main or auxiliary systems of gas centrifuge enrichment plants. EXPLANATORY NOTE Typical especially designed or prepared valves include bellow-sealed valves, fast acting closure-types, fast acting valves and others.

0B001.c Equipment and components, specially designed or prepared for gaseous diffusion separation process, as follows: 1. Gaseous diffusion barriers made of porous metallic, polymer or ceramic “materials resistant to corrosion by UF6” with a pore size of 10 to 100 nm, a thickness of 5 mm or less, and, for tubular forms, a diameter of 25 mm or less; TLB5.3.1a Gaseous diffusion barriers and barrier materials (a) Especially designed or prepared thin, porous filters, with a pore size of 10 — 100 nm, a thickness of 5 mm or less, and for tubular forms, a diameter of 25 mm or less, made of metallic, polymer or ceramic materials resistant to corrosion by UF6 (see EXPLANATORY NOTE to section 5.4), and

0B001.c 2. Gaseous diffuser housings made of or protected by “materials resistant to corrosion by UF6”; TLB5.3.2 Diffuser housings Especially designed or prepared hermetically sealed vessels for containing the gaseous diffusion barrier, made of or protected by UF6-resistant materials (see EXPLANATORY NOTE to section 5.4).

0B001.c 3. Compressors or gas blowers with a suction volume capacity of 1 m3/min or more of UF6, discharge pressure up to 500 kPa and having a pressure ratio of 10:1 or less, and made of or protected by “materials resistant to corrosion by UF6”; TLB5.3.3 Compressors and gas blowers Especially designed or prepared compressors or gas blowers with a suction volume capacity of 1 m3 per minute or more of UF6, and with a discharge pressure of up to 500 kPa, designed for long-term operation in the UF6 environment, as well as separate 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 protected by, materials resistant to UF6 (see EXPLANATORY NOTE to section 5.4).

0B001.c 4. Rotary shaft seals for compressors or blowers specified in 0B001.c.3. and designed for a buffer gas in-leakage rate of less than 1 000 cm3/min.; TLB5.3.4 Rotary shaft seals Especially designed or prepared vacuum seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor or the gas blower rotor with the driver motor so as to ensure a reliable seal against in-leaking of air into the inner chamber of the compressor or gas blower which is filled with UF6. Such seals are normally designed for a buffer gas in-leakage rate of less than 1 000 cm3 per minute.

0B001.c 5. Heat exchangers made of or protected by “materials resistant to corrosion by UF6”, and designed for a leakage pressure rate of less than 10 Pa per hour under a pressure differential of 100 kPa TLB5.3.5 Heat exchangers for cooling UF6 Especially designed or prepared heat exchangers made of or protected by UF6-resistant materials (see EXPLANATORY NOTE to section 5.4), and intended for a leakage pressure change rate of less than 10 Pa per hour under a pressure difference of 100 kPa.

0B001.c 6. Bellows-sealed valves, manual or automated, shut-off or control, made of or protected by “materials resistant to corrosion by UF6”; TLB5.4.4 Special shut-off and control valves Especially designed or prepared bellows-sealed valves, manual or automated, shut-off or control, made of or protected by materials resistant to corrosion by UF6, for installation in main and auxiliary systems of gaseous diffusion enrichment plants.

0B001.d Equipment and components, specially designed or prepared for aerodynamic separation process, as follows: 1. Separation nozzles consisting of slit-shaped, curved channels having a radius of curvature less than 1 mm, resistant to corrosion by UF6, and having a knife-edge contained within the nozzle which separates the gas flowing through the nozzle into two streams; TLB5.5.1 Separation nozzles Especially designed or prepared separation nozzles and assemblies thereof. The separation nozzles consist of slit-shaped, curved channels having a radius of curvature less than 1 mm, resistant to corrosion by UF6 and having a knife-edge within the nozzle that separates the gas flowing through the nozzle into two fractions.

0B001.d 2. Cylindrical or conical tubes, (vortex tubes), made of or protected by “materials resistant to corrosion by UF6” and with one or more tangential inlets; TLB5.5.2 Vortex tubes Especially designed or prepared vortex tubes and assemblies thereof. The vortex tubes are cylindrical or tapered, made of or protected by materials resistant to corrosion by UF6, and with one or more tangential inlets. The tubes may be equipped with nozzletype appendages at either or both ends. EXPLANATORY NOTE The feed gas enters the vortex tube tangentially at one end or through swirl vanes or at numerous tangential positions along the periphery of the tube.

0B001.d 3. Compressors or gas blowers made of or protected by “materials resistant to corrosion by UF6”, and rotary shaft seals therefor; TLB5.5.3 TLB5.5.4 Compressors and gas blowers Especially designed or prepared compressors or gas blowers made of or protected by materials resistant to corrosion by the UF6/carrier gas (hydrogen or helium) mixture. Rotary shaft seals Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor rotor or the gas blower rotor with the driver motor so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or seal gas into the inner chamber of the compressor or gas blower which is filled with a UF6/carrier gas mixture.

0B001.d 4. Heat exchangers made of or protected by “materials resistant to corrosion by UF6”; TLB5.5.5 Heat exchangers for gas cooling Especially designed or prepared heat exchangers made of or protected by materials resistant to corrosion by UF6.

0B001.d 5. Separation element housings, made of or protected by “materials resistant to corrosion by UF6” to contain vortex tubes or separation nozzles; TLB5.5.6 Separation element housings Especially designed or prepared separation element housings, made of or protected by materials resistant to corrosion by UF6, for containing vortex tubes or separation nozzles.

0B001.d 6. Bellows-sealed valves, manual or automated, shut-off or control, made of or protected by “materials resistant to corrosion by UF6”, with a diameter of 40 mm or more; TLB5.5.10 UF6 mass spectrometers/Ion sources Especially designed or prepared mass spectrometers capable of taking on-line samples from UF6 gas streams and having all of the following: 1. Capable of measuring ions of 320 atomic mass units or greater and having a resolution of better than 1 part in 320; 2. Ion sources constructed of or protected by nickel, nickel-copper alloys with a nickel content of 60 % or more by weight, or nickel-chrome alloys; 3. Electron bombardment ionization sources; 4. Having a collector system suitable for isotopic analysis.

0B001.d 7. Process systems for separating UF6 from carrier gas (hydrogen or helium) to 1 ppm UF6 content or less, including: a. Cryogenic heat exchangers and cryoseparators capable of temperatures of 153K (–120 °C) or less; b. Cryogenic refrigeration units capable of temperatures of 153 K (–120 °C) or less; c. Separation nozzle or vortex tube units for the separation of UF6 from carrier gas; d. UF6 cold traps capable of freezing out UF6; TLB5.5.12 UF6/carrier gas separation systems Especially designed or prepared process systems for separating UF6 from carrier gas (hydrogen or helium). EXPLANATORY NOTE These systems are designed to reduce the UF6 content in the carrier gas to 1 ppm or less and may incorporate equipment such as: (a) Cryogenic heat exchangers and cryoseparators capable of temperatures of 153 K (– 120 °C) or less, or (b) Cryogenic refrigeration units capable of temperatures of 153 K (–120 °C) or less, or (c) Separation nozzle or vortex tube units for the separation of UF6 from carrier gas, or (d) UF6 cold traps capable of freezing out UF6.

0B001.e Equipment and components, specially designed or prepared for chemical exchange separation process, as follows: 1. Fast-exchange liquid-liquid pulse columns with stage residence time of 30 seconds or less and resistant to concentrated hydrochloric acid (e.g. made of or protected by suitable plastic materials such as fluorinated hydrocarbon polymers or glass) TLB5.6.1 Liquid-liquid exchange columns (Chemical exchange) Countercurrent liquid-liquid exchange columns having mechanical power input, especially designed or prepared for uranium enrichment using the chemical exchange process. For corrosion resistance to concentrated hydrochloric acid solutions, these columns and their internals are normally made of or protected by suitable plastic materials (such as fluorinated hydrocarbon polymers) or glass. The stage residence time of the columns is normally designed to be 30 seconds or less.

0B001.e 2. Fast-exchange liquid-liquid centrifugal contactors with stage residence time of 30 seconds or less and resistant to concentrated hydrochloric acid (e.g. made of or protected by suitable plastic materials such as fluorinated hydrocarbon polymers or glass); TLB5.6.2 Liquid-liquid centrifugal contactors (Chemical exchange) Liquid-liquid centrifugal contactors especially designed or prepared for uranium enrichment using the chemical exchange process. Such contactors use rotation to achieve dispersion of the organic and aqueous streams and then centrifugal force to separate the phases. For corrosion resistance to concentrated hydrochloric acid solutions, the contactors are normally made of or protected by suitable plastic materials (such as fluorinated hydrocarbon polymers) or glass. The stage residence time of the centrifugal contactors is normally designed to be 30 seconds or less.

0B001.e 3. Electrochemical reduction cells resistant to concentrated hydrochloric acid solutions, for reduction of uranium from one valence state to another; TLB5.6.3a Uranium reduction systems and equipment (Chemical exchange) (a) Especially designed or prepared electrochemical reduction cells to reduce uranium from one valence state to another for uranium enrichment using the chemical exchange process. The cell materials in contact with process solutions must be corrosion resistant to concentrated hydrochloric acid solutions. EXPLANATORY NOTE The cell cathodic compartment must be designed to prevent re-oxidation of uranium to its higher valence state. To keep the uranium in the cathodic compartment, the cell may have an impervious diaphragm membrane constructed of special cation exchange material. The cathode consists of a suitable solid conductor such as graphite.

0B001.e 4. Electrochemical reduction cells feed equipment to take U+4 from the organic stream and, for those parts in contact with the process stream, made of or protected by suitable materials (e.g. glass, fluorocarbon polymers, polyphenyl sulphate, polyether sulfone and resin-impregnated graphite); TLB5.6.3b (b) Especially designed or prepared systems at the product end of the cascade for taking the U+4 out of the organic stream, adjusting the acid concentration and feeding to the electrochemical reduction cells. EXPLANATORY NOTE These systems consist of solvent extraction equipment for stripping the U+4 from the organic stream into an aqueous solution, evaporation and/or other equipment to accomplish solution pH adjustment and control, and pumps or other transfer devices for feeding to the electrochemical reduction cells. A major design concern is to avoid contamination of the aqueous stream with certain metal ions. Consequently, for those parts in contact with the process stream, the system is constructed of equipment made of or protected by suitable materials (such as glass, fluorocarbon polymers, polyphenyl sulfate, polyether sulfone, and resinimpregnated graphite).

0B001.e 5. Feed preparation systems for producing high purity uranium chloride solution consisting of dissolution, solvent extraction and/or ion exchange equipment for purification and electrolytic cells for reducing the uranium U+6 or U+4 to U+3; TLB5.6.4 Feed preparation systems (Chemical exchange) Especially designed or prepared systems for producing high-purity uranium chloride feed solutions for chemical exchange uranium isotope separation plants. EXPLANATORY NOTE These systems consist of dissolution, solvent extraction and/or ion exchange equipment for purification and electrolytic cells for reducing the uranium U+6 or U+4 to U+3. These systems produce uranium chloride solutions having only a few parts per million of metallic impurities such as chromium, iron, vanadium, molybdenum and other bivalent or higher multi-valent cations. Materials of construction for portions of the system processing high-purity U+3 include glass, fluorinated hydrocarbon polymers, polyphenyl sulfate or polyether sulfone plastic-lined and resin-impregnated graphite. NSG Part 1 June 2013 - 39 - 5.6.5. Uranium

0B001.e 6. Uranium oxidation systems for oxidation of U+3 to U+4; TLB5.6.5 Uranium oxidation systems (Chemical exchange) Especially designed or prepared systems for oxidation of U+3 to U+4 for return to the uranium isotope separation cascade in the chemical exchange enrichment process. EXPLANATORY NOTE These systems may incorporate equipment such as: (a) Equipment for contacting chlorine and oxygen with the aqueous effluent from the isotope separation equipment and extracting the resultant U+4 into the stripped organic stream returning from the product end of the cascade, (b) Equipment that separates water from hydrochloric acid so that the water and the concentrated hydrochloric acid may be reintroduced to the process at the proper locations.

0B001.f Equipment and components, specially designed or prepared for ion-exchange separation process, as follows: 1. Fast reacting ion-exchange resins, pellicular or porous macro-reticulated resins in which the active chemical exchange groups are limited to a coating on the surface of an inactive porous support structure, and other composite structures in any suitable form, including particles or fibres, with diameters of 0,2 mm or less, resistant to concentrated hydrochloric acid and designed to have an exchange rate half-time of less than 10 seconds and capable of operating at temperatures in the range of 373 K (100 °C) to 473 K (200 °C); TLB5.6.6 Fast-reacting ion exchange resins/adsorbents (Ion exchange) Fast-reacting ion-exchange resins or adsorbents especially designed or prepared for uranium enrichment using the ion exchange process, including porous macroreticular resins, and/or pellicular structures in which the active chemical exchange groups are limited to a coating on the surface of an inactive porous support structure, and other composite structures in any suitable form including particles or fibres. These ion exchange resins/adsorbents have diameters of 0,2 mm or less and must be chemically resistant to concentrated hydrochloric acid solutions as well as physically strong enough so as not to degrade in the exchange columns. The resins/adsorbents are especially designed to achieve very fast uranium isotope exchange kinetics (exchange rate half-time of less than 10 seconds) and are capable of operating at a temperature in the range of 373 K (100 °C) to 473 K (200 °C).

0B001.f 2. Ion exchange columns (cylindrical) with a diameter greater than 1 000 mm, made of or protected by materials resistant to concentrated hydrochloric acid (e.g. titanium or fluorocarbon plastics) and capable of operating at temperatures in the range of 373 K (100 °C) to 473 K (200 °C) and pressures above 0,7 MPa; TLB5.6.7 Ion exchange columns (Ion exchange) Cylindrical columns greater than 1 000 mm in diameter for containing and supporting packed beds of ion exchange resin/adsorbent, especially designed or prepared for uranium enrichment using the ion exchange process. These columns are made of or protected by materials (such as titanium or fluorocarbon plastics) resistant to corrosion by concentrated hydrochloric acid solutions and are capable of operating at a temperature in the range of 373 K (100 °C) to 473 K (200 °C) and pressures above 0,7 MPa.

0B001.f 3. Ion exchange reflux systems (chemical or electrochemical oxidation or reduction systems) for regeneration of the chemical reducing or oxidizing agents used in ion exchange enrichment cascades; TLB5.6.8 Ion exchange reflux systems (Ion exchange) (a) Especially designed or prepared chemical or electrochemical reduction systems for regeneration of the chemical reducing agent(s) used in ion exchange uranium enrichment cascades. (b) Especially designed or prepared chemical or electrochemical oxidation systems for regeneration of the chemical oxidizing agent(s) used in ion exchange uranium enrichment cascades.

0B001.g Equipment and components, specially designed or prepared for laser-based separation processes using atomic vapour laser isotope separation, as follows: 1. Uranium metal vaporization systems designed to achieve a delivered power of 1 kW or more on the target for use in laser enrichment; TLB5.7.1 Uranium vaporization systems (atomic vapour based methods) Especially designed or prepared uranium metal vaporization systems for use in laser enrichment. EXPLANATORY NOTE These systems may contain electron beam guns and are designed to achieve a delivered power (1 kW or greater) on the target sufficient to generate uranium metal vapour at a rate required for the laser enrichment function.

0B001.g 2. Liquid or vapour uranium metal handling systems specially designed or prepared for handling molten uranium, molten uranium alloys or uranium metal vapour for use in laser enrichment, and specially designed components therefor; N.B.: SEE ALSO 2A225. TLB5.7.2 Liquid or vapour uranium metal handling systems and components (atomic vapour based methods) Especially designed or prepared systems for handling molten uranium, molten uranium alloys or uranium metal vapour for use in laser enrichment or especially designed or prepared components therefore. EXPLANATORY NOTE The liquid uranium metal handling systems may consist of crucibles and cooling equipment for the crucibles. The crucibles and other parts of this system that come into contact with molten uranium, molten uranium alloys or uranium metal vapour are made of or protected by materials of suitable corrosion and heat resistance. Suitable materials may include tantalum, yttria-coated graphite, graphite coated with other rare earth oxides (see INFCIRC/254/Part 2 — (as amended)) or mixtures thereof.

0B001.g 3. Product and tails collector assemblies for uranium metal in liquid or solid form, made of or protected by materials resistant to the heat and corrosion of uranium metal vapour or liquid, such as yttria-coated graphite or tantalum; TLB5.7.3 Uranium metal ‘product’ and ‘tails’ collector assemblies (atomic vapour based methods) Especially designed or prepared ‘product’ and ‘tails’ collector assemblies for uranium metal in liquid or solid form. EXPLANATORY NOTE Components for these assemblies are made of or protected by materials resistant to the heat and corrosion of uranium metal vapour or liquid (such as yttria-coated graphite or tantalum) and may include pipes, valves, fittings, ‘gutters’, feed-throughs, heat exchangers and collector plates for magnetic, electrostatic or other separation methods.

0B001.g 4. Separator module housings (cylindrical or rectangular vessels) for containing the uranium metal vapour source, the electron beam gun and the product and tails collectors; TLB5.7.4 Separator module housings (atomic vapour based methods) Especially designed or prepared cylindrical or rectangular vessels for containing the uranium metal vapour source, the electron beam gun, and the ‘product’ and ‘tails’ collectors. EXPLANATORY NOTE These housings have multiplicity of ports for electrical and water feed-throughs, laser beam windows, vacuum pump connections and instrumentation diagnostics and monitoring. They have provisions for opening and closure to allow refurbishment of internal components.

0B001.g 5. “Lasers” or “laser” systems specially designed or prepared for the separation of uranium isotopes with a spectrum frequency stabilisation for operation over extended periods of time; N.B.: SEE ALSO 6A005 AND 6A205. TLB5.7.13 Laser systems Lasers or laser systems especially designed or prepared for the separation of uranium isotopes. EXPLANATORY NOTE The lasers and laser components of importance in laser-based enrichment processes include those identified in INFCIRC/254/Part 2 — (as amended). The laser system typically contains both optical and electronic components for the management of the laser beam (or beams) and the transmission to the isotope separation chamber. The laser system for atomic vapour based methods usually consists of tunable dye lasers pumped by another type of laser (e.g., copper vapour lasers or certain solid-state lasers). The laser system for molecular based methods may consist of CO2 lasers or excimer lasers and a multi-pass optical cell. Lasers or laser systems for both methods require spectrum frequency stabilization for operation over extended periods of time.

0B001.h Equipment and components, specially designed or prepared for laser-based separation processes using molecular laser isotope separation, as follows: 1. Supersonic expansion nozzles for cooling mixtures of UF6 and carrier gas to 150 K (–123 °C) or less and made from “materials resistant to corrosion by UF6”; TLB5.7.5 Supersonic expansion nozzles (molecular based methods) Especially designed or prepared supersonic expansion nozzles for cooling mixtures of UF6 and carrier gas to 150 K (–123 °C) or less and which are corrosion resistant to UF6.

0B001.h 2. Product or tails collector components or devices specially designed or prepared for collecting uranium material or uranium tails material following illumination with laser light, made of “materials resistant to corrosion by UF6”; TLB5.7.6 ‘Product’ or ‘tails’ collectors (molecular based methods) Especially designed or prepared components or devices for collecting uranium product material or uranium tails material following illumination with laser light. EXPLANATORY NOTE In one example of molecular laser isotope separation, the product collectors serve to collect enriched uranium pentafluoride (UF5) solid material. The product collectors may consist of filter, impact, or cyclone-type collectors, or combinations thereof, and must be corrosion resistant to the UF5/ UF6 environment.

0B001.h 3. Compressors made of or protected by “materials resistant to corrosion by UF6”, and rotary shaft seals therefor; TLB5.7.7 UF6/carrier gas compressors (molecular based methods) Especially designed or prepared compressors for UF6/carrier gas mixtures, designed for long term operation in a UF6 environment. The components of these compressors that come into contact with process gas are made of or protected by materials resistant to corrosion by UF6.

TLB5.7.8 Rotary shaft seals (molecular based methods) Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust connections, for sealing the shaft connecting the compressor rotor with the driver motor so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or seal gas into the inner chamber of the compressor which is filled with a UF6/carrier gas mixture.

0B001.h 4. Equipment for fluorinating UF5 (solid) to UF6 (gas); TLB5.7.9 Fluorination systems (molecular based methods) Especially designed or prepared systems for fluorinating UF5 (solid) to UF6 (gas). EXPLANATORY NOTE These systems are designed to fluorinate the collected UF5 powder to UF6 for subsequent collection in product containers or for transfer as feed for additional enrichment. In one approach, the fluorination reaction may be accomplished within the isotope separation system to react and recover directly off the ‘product’ collectors. In another approach, the UF5 powder may be removed/transferred from the ‘product’ collectors into a suitable reaction vessel (e.g., fluidized-bed reactor, screw reactor or flame tower) for fluorination. In both approaches, equipment for storage and transfer of fluorine (or other suitable fluorinating agents) and for collection and transfer of UF6 are used.

0B001.h 5. Process systems for separating UF6 from carrier gas (e.g. nitrogen, argon or other gas) including: a. Cryogenic heat exchangers and cryoseparators capable of temperatures of 153 K (–120 °C) or less; b. Cryogenic refrigeration units capable of temperatures of 153 K (–120 °C) or less; c. UF6 cold traps capable of freezing out UF6; TLB5.7.12 UF6/carrier gas separation systems (molecular based methods) Especially designed or prepared process systems for separating UF6 from carrier gas. EXPLANATORY NOTE These systems may incorporate equipment such as: (a) Cryogenic heat exchangers or cryoseparators capable of temperatures of 153 K (– 120 °C) or less, or (b) Cryogenic refrigeration units capable of temperatures of 153 K (–120 °C) or less, or (c) UF6 cold traps capable of freezing out UF6. The carrier gas may be nitrogen, argon, or other gas.

0B001.h 6. “Lasers” or “laser” systems specially designed or prepared for the separation of uranium isotopes with a spectrum frequency stabilisation for operation over extended periods of time; N.B.: SEE ALSO 6A005 AND 6A205. TLB5.7.13 Laser systems Lasers or laser systems especially designed or prepared for the separation of uranium isotopes. EXPLANATORY NOTE The lasers and laser components of importance in laser-based enrichment processes include those identified in INFCIRC/254/Part 2 — (as amended). The laser system typically contains both optical and electronic components for the management of the laser beam (or beams) and the transmission to the isotope separation chamber. The laser system for atomic vapour based methods usually consists of tunable dye lasers pumped by another type of laser (e.g., copper vapour lasers or certain solid-state lasers). The laser system for molecular based methods may consist of CO2 lasers or excimer lasers and a multi-pass optical cell. Lasers or laser systems for both methods require spectrum frequency stabilization for operation over extended periods of time.

0B001.i Equipment and components, specially designed or prepared for plasma separation process, as follows: 1. Microwave power sources and antennae for producing or accelerating ions, with an output frequency greater than 30 GHz and mean power output greater than 50 kW; TLB5.8.1 Microwave power sources and antennae Especially designed or prepared microwave power sources and antennae for producing or accelerating ions and having the following characteristics: greater than 30 GHz frequency and greater than 50 kW mean power output for ion production.

0B001.i 2. Radio frequency ion excitation coils for frequencies of more than 100 kHz and capable of handling more than 40 kW mean power; TLB5.8.2 Ion excitation coils Especially designed or prepared radio frequency ion excitation coils for frequencies of more than 100 kHz and capable of handling more than 40 kW mean power.

0B001.i 3. Uranium plasma generation systems; TLB5.8.3 Uranium plasma generation systems Especially designed or prepared systems for the generation of uranium plasma for use in plasma separation plants.

0B001.i 4. Not used; TLB5.8.4 No longer used — since 14 June 2013

0B001.i 5. Product and tails collector assemblies for uranium metal in solid form, made of or protected by materials resistant to the heat and corrosion of uranium vapour such as yttria-coated graphite or tantalum; TLB5.8.5 Uranium metal ‘product’ and ‘tails’ collector assemblies Especially designed or prepared ‘product’ and ‘tails’ collector assemblies for uranium metal in solid form. These collector assemblies are made of or protected by materials resistant to the heat and corrosion of uranium metal vapor, such as yttria-coated graphite or tantalum.

0B001.i 6. Separator module housings (cylindrical) for containing the uranium plasma source, radio-frequency drive coil and the product and tails collectors and made of a suitable non-magnetic material (e.g. stainless steel); TLB.5.8.6 Separator module housings Cylindrical vessels especially designed or prepared for use in plasma separation enrichment plants for containing the uranium plasma source, radio-frequency drive coil and the “product” and “tails” collectors. EXPLANATORY NOTE These housings have a multiplicity of ports for electrical feed-throughs, diffusion pump connections and instrumentation diagnostics and monitoring. They have provisions for opening and closure to allow for refurbishment of internal components and are constructed of a suitable non-magnetic material such as stainless steel.

0B001.j Equipment and components, specially designed or prepared for electromagnetic separation process, as follows: 1. Ion sources, single or multiple, consisting of a vapour source, ioniser, and beam accelerator made of suitable non-magnetic materials (e.g. graphite, stainless steel, or copper) and capable of providing a total ion beam current of 50 mA or greater; TLB5.9.1a Electromagnetic isotope separators Electromagnetic isotope separators especially designed or prepared for the separation of uranium isotopes, and equipment and components therefor, including: (a) Ion sources Especially designed or prepared single or multiple uranium ion sources consisting of a vapour source, ionizer, and beam accelerator, constructed of suitable materials such as graphite, stainless steel, or copper, and capable of providing a total ion beam current of 50 mA or greater.

0B001.j 2. Ion collector plates for collection of enriched or depleted uranium ion beams, consisting of two or more slits and pockets and made of suitable non-magnetic materials (e.g. graphite or stainless steel); TLB5.9.1b Ion collectors Collector plates consisting of two or more slits and pockets especially designed or prepared for collection of enriched and depleted uranium ion beams and constructed of suitable materials such as graphite or stainless steel.

0B001.j 3. Vacuum housings for uranium electromagnetic separators made of non-magnetic materials (e.g. stainless steel) and designed to operate at pressures of 0,1 Pa or lower; TLB5.9.1c Vacuum housings Especially designed or prepared vacuum housings for uranium electromagnetic separators, constructed of suitable non-magnetic materials such as stainless steel and designed for operation at pressures of 0,1 Pa or lower. EXPLANATORY NOTE The housings are specially designed to contain the ion sources, collector plates and water-cooled liners and have provision for diffusion pump connections and opening and closure for removal and reinstallation of these components.

0B001.j 4. Magnet pole pieces with a diameter greater than 2 m; TLB5.9.1d Magnet pole pieces Especially designed or prepared magnet pole pieces having a diameter greater than 2 m used to maintain a constant magnetic field within an electromagnetic isotope separator and to transfer the magnetic field between adjoining separators.

0B001.j 5. High voltage power supplies for ion sources, having all of the following characteristics: a. Capable of continuous operation; b. Output voltage of 20 000 V or greater; c. Output current of 1 A or greater; and d. Voltage regulation of better than 0,01 % over a period of 8 hours; N.B.: SEE ALSO 3A227. TLB5.9.2 High voltage power supplies Especially designed or prepared high-voltage power supplies for ion sources, having all of the following characteristics: capable of continuous operation, output voltage of 20 000 V or greater, output current of 1 A or greater, and voltage regulation of better than 0,01 % over a time period of 8 hours.

0B001.j 6. Magnet power supplies (high power, direct current) having all of the following characteristics: a. Capable of continuous operation with a current output of 500 A or greater at a voltage of 100 V or greater; and b. Current or voltage regulation better than 0,01 % over a period of 8 hours. N.B.: SEE ALSO 3A226. TLB5.9.3 Magnet power supplies Especially designed or prepared high-power, direct current magnet power supplies having all of the following characteristics: capable of continuously producing a current output of 500 A or greater at a voltage of 100 V or greater and with a current or voltage regulation better than 0,01 % over a period of 8 hours.

0B002 Specially designed or prepared auxiliary systems, equipment and components, as follows, for isotope separation plant specified in 0B001, made of or protected by “materials resistant to corrosion by UF6”:

0B002.a Feed autoclaves, ovens or systems used for passing UF6 to the enrichment process; TLB5.2.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.4.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.5.7 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers

TLB5.7.11 Feed systems/product and tails withdrawal systems (molecular based methods) Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

0B002.b Desublimers or cold traps, used to remove UF6 from the enrichment process for subsequent transfer upon heating; TLB5.2.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.4.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.5.7 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.7.11 Feed systems/product and tails withdrawal systems (molecular based methods) Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

0B002.c Product and tails stations for transferring UF6 into containers; TLB5.2.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.4.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.5.7 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.7.11 Feed systems/product and tails withdrawal systems (molecular based methods) Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

0B002.d Liquefaction or solidification stations used to remove UF6 from the enrichment process by compressing, cooling and converting UF6 to a liquid or solid form; TLB5.2.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.4.1 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers, cold traps or pumps used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.5.7 Feed systems/product and tails withdrawal systems Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

TLB5.7.11 Feed systems/product and tails withdrawal systems (molecular based methods) Especially designed or prepared process systems or equipment for enrichment plants made of or protected by materials resistant to corrosion by UF6, including: (a) Feed autoclaves, ovens, or systems used for passing UF6 to the enrichment process; (b) Desublimers (or cold traps) used to remove UF6 from the enrichment process for subsequent transfer upon heating; (c) Solidification or liquefaction stations used to remove UF6 from the enrichment process by compressing and converting UF6 to a liquid or solid form; (d) ‘Product’ or ‘tails’ stations used for transferring UF6 into containers.

0B002.e Piping systems and header systems specially designed or prepared for handling UF6 within gaseous diffusion, centrifuge or aerodynamic cascades; TLB5.2.2 Machine header piping systems Especially designed or prepared piping systems and header systems for handling UF6 within the centrifuge cascades. The piping network is normally of the ‘triple’ header system with each centrifuge connected to each of the headers. There is thus a substantial amount of repetition in its form. It is wholly made of or protected by UF6-resistant materials (see EXPLANATORY NOTE to this section) and is fabricated to very high vacuum and cleanliness standards.

TLB5.4.2 Header piping systems Especially designed or prepared piping systems and header systems for handling UF6 within the gaseous diffusion cascades. EXPLANATORY NOTE This piping network is normally of the “double” header system with each cell connected to each of the headers.

TLB5.5.8 Header piping systems Especially designed or prepared header piping systems, made of or protected by materials resistant to corrosion by UF6, for handling UF6 within the aerodynamic cascades. This piping network is normally of the ‘double’ header design with each stage or group of stages connected to each of the headers.

0B002.f Vacuum systems and pumps as follows: 1. Vacuum manifolds, vacuum headers or vacuum pumps having a suction capacity of 5 m3/minute or more; 2. Vacuum pumps specially designed for use in UF6 bearing atmospheres made of, or protected by, “materials resistant to corrosion by UF6”; or 3. Vacuum systems consisting of vacuum manifolds, vacuum headers and vacuum pumps, and designed for service in UF6-bearing atmospheres; TLB5.4.3a Vacuum systems (a) Especially designed or prepared vacuum manifolds, vacuum headers and vacuum pumps having a suction capacity of 5 m3 per minute or more.

TLB5.4.3b (b) Vacuum pumps especially designed for service in UF6-bearing atmospheres made of, or protected by, materials resistant to corrosion by UF6 (see EXPLANATORY NOTE to this section). These pumps may be either rotary or positive, may have displacement and fluorocarbon seals, and may have special working fluids present.

TLB5.5.9b Vacuum systems and pumps Vacuum pumps especially designed or prepared for service in UF6-bearing atmospheres and made of or protected by materials resistant to corrosion by UF6. These pumps may use fluorocarbon seals and special working fluids.

TLB5.5.9a Especially designed or prepared vacuum systems consisting of vacuum manifolds, vacuum headers and vacuum pumps, and designed for service in UF6-bearing atmospheres

0B002.g UF6 mass spectrometers/ion sources capable of taking on-line samples from UF6 gas streams and having all of the following: 1. Capable of measuring ions of 320 atomic mass units or greater and having a resolution of better than 1 part in 320; 2. Ion sources constructed of or protected by nickel, nickel-copper alloys with a nickel content of 60 % or more by weight, or nickel-chrome alloys; 3. Electron bombardment ionisation sources; and 4. Having a collector system suitable for isotopic analysis. TLB5.2.4 UF6 mass spectrometers/ion sources Especially designed or prepared mass spectrometers capable of taking on-line samples from UF6 gas streams and having all of the following: 1. Capable of measuring ions of 320 atomic mass units or greater and having a resolution of better than 1 part in 320; 2. Ion sources constructed of or protected by nickel, nickel-copper alloys with a nickel content of 60 % or more by weight, or nickel-chrome alloys; 3. Electron bombardment ionization sources; 4. Having a collector system suitable for isotopic analysis.

TLB5.4.5 UF6 mass spectrometers/ion sources Especially designed or prepared mass spectrometers capable of taking on-line samples from UF6 gas streams and having all of the following: 1. Capable of measuring ions of 320 atomic mass units or greater and having a resolution of better than 1 part in 320; 2. Ion sources constructed of or protected by nickel, nickel-copper alloys with a nickel content of 60 % or more by weight, or nickel-chrome alloys; 3. Electron bombardment ionization sources; 4. Having a collector system suitable for isotopic analysis.

TLB5.5.11 UF6 mass spectrometers/Ion sources Especially designed or prepared mass spectrometers capable of taking on-line samples from UF6 gas streams and having all of the following: 1. Capable of measuring ions of 320 atomic mass units or greater and having a resolution of better than 1 part in 320; 2. Ion sources constructed of or protected by nickel, nickel-copper alloys with a nickel content of 60 % or more by weight, or nickel-chrome alloys; 3. Electron bombardment ionization sources; 4. Having a collector system suitable for isotopic analysis.

TLB5.7.10 Special shut-off and control valves Especially designed or prepared bellows-sealed valves, manual or automated, shut-off or control, made of or protected by materials resistant to corrosion by UF6, with a diameter of 40 mm or greater, for installation in main and auxiliary systems of aerodynamic enrichment plants.

0B003 Plant for the conversion of uranium and equipment specially designed or prepared therefor, as follows: TLB7.1 Especially designed or prepared systems for the conversion of uranium ore concentrates to UO3

0B003.a Systems for the conversion of uranium ore concentrates to UO3; TLB7.1.1 EXPLANATORY NOTE Conversion of uranium ore concentrates to UO3 can be performed by first dissolving the ore in nitric acid and extracting purified uranyl nitrate using a solvent such as tributyl phosphate. Next, the uranyl nitrate is converted to UO3 either by concentration and denitration or by neutralization with gaseous ammonia to produce ammonium diuranate with subsequent filtering, drying, and calcining

0B003.b Systems for the conversion of UO3 to UF6; TLB7.1.2 Especially designed or prepared systems for the conversion of UO3 to UF6 EXPLANATORY NOTE EXPLANATORY NOTE Conversion of UO3 to UO2 can be performed through reduction of UO3 with cracked ammonia gas or hydrogen.

0B003.c Systems for the conversion of UO3 to UO2; TLB7.1.3 Especially designed or prepared systems for the conversion of UO3 to UO2 EXPLANATORY NOTE Conversion of UO3 to UO2 can be performed through reduction of UO3 with cracked ammonia gas or hydrogen.

0B003.d Systems for the conversion of UO2 to UF4; TLB7.1.4 Especially designed or prepared systems for the conversion of UO2 to UF4 EXPLANATORY NOTE Conversion of UO2 to UF4 can be performed by reacting UO2 with hydrogen fluoride gas (HF) at 300-500 °C.

0B003.e Systems for the conversion of UF4 to UF6; TLB7.1.5 Especially designed or prepared systems for the conversion of UF4 to UF6 EXPLANATORY NOTE Conversion of UF4 to UF6 is performed by exothermic reaction with fluorine in a tower reactor. UF6 is condensed from the hot effluent gases by passing the effluent stream through a cold trap cooled to –10 °C. The process requires a source of fluorine gas

0B003.f Systems for the conversion of UF4 to uranium metal; TLB7.1.6 Especially designed or prepared systems for the conversion of UF4 to U metal EXPLANATORY NOTE Conversion of UF4 to U metal is performed by reduction with magnesium (large batches) or calcium (small batches). The reaction is carried out at temperatures above the melting point of uranium (1 130 °C).

0B003.g Systems for the conversion of UF6 to UO2; TLB7.1.7 Especially designed or prepared systems for the conversion of UF6 to UO2 EXPLANATORY NOTE Conversion of UF6 to UO2 can be performed by one of three processes. In the first, UF6 is reduced and hydrolyzed to UO2 using hydrogen and steam. In the second, UF6 is hydrolyzed by solution in water, ammonia is added to precipitate ammonium diuranate, and the diuranate is reduced to UO2 with hydrogen at 820 °C. In the third process, gaseous UF6, CO2, and NH3 are combined in water, precipitating ammonium uranyl carbonate. The ammonium uranyl carbonate is combined with steam and hydrogen at 500-600 °C to yield UO2. UF6 to UO2 conversion is often performed as the first stage of a fuel fabrication plant.

0B003.h Systems for the conversion of UF6 to UF4; TLB7.1.8 Especially designed or prepared systems for the conversion of UF6 to UF4 EXPLANATORY NOTE Conversion of UF6 to UF4 is performed by reduction with hydrogen.

0B003.i Systems for the conversion of UO2 to UCl4. TLB7.1.9 Especially designed or prepared systems for the conversion of UO2 to UCl4 EXPLANATORY NOTE Conversion of UO2 to UCl4 can be performed by one of two processes. In the first, UO2 is reacted with carbon tetrachloride (CCl4) at approximately 400 °C. In the second, UO2 is reacted at approximately 700 °C in the presence of carbon black (CAS 1333-86-4), carbon monoxide, and chlorine to yield UCl4.

0B004 Plant for the production or concentration of heavy water, deuterium and deuterium compounds and specially designed or prepared equipment and components therefor, as follows: TLB6 Plants for the production or concentration of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor:

0B004.a Plant for the production of heavy water, deuterium or deuterium compounds, as follows: 1. Water-hydrogen sulphide exchange plants; 2. Ammonia-hydrogen exchange plants;

0B004.b Equipment and components, as follows:

1. Water-hydrogen sulphide exchange towers with diameters of 1,5 m or more, capable of operating at pressures greater than or equal to 2 MPa; TLB6.1 Water — Hydrogen Sulphide Exchange Towers Exchange towers with diameters of 1,5 m or greater and capable of operating at pressures greater than or equal to 2 MPa (300 psi), especially designed or prepared for heavy water production utilizing the water-hydrogen sulphide exchange process.

2. Single stage, low head (i.e. 0,2 MPa) centrifugal blowers or compressors for hydrogen sulphide gas circulation (i.e. gas containing more than 70 % H2S) with a throughput capacity greater than or equal to 56 m3/second when operating at pressures greater than or equal to 1,8 MPa suction and having seals designed for wet H2S service; TLB6.2 Blowers and Compressors Single stage, low head (i.e., 0,2 MPa or 30 psi) centrifugal blowers or compressors for hydrogen-sulphide gas circulation (i.e., gas containing more than 70 % H2S) especially designed or prepared for heavy water production utilizing the water-hydrogen sulphide exchange process. These blowers or compressors have a throughput capacity greater than or equal to 56 m3/second (120 000 SCFM) while operating at pressures greater than or equal to 1,8 MPa (260 psi) suction and have seals designed for wet H2S service.

3. Ammonia-hydrogen exchange towers greater than or equal to 35 m in height with diameters of 1,5 m to 2,5 m capable of operating at pressures greater than 15 MPa; TLB6.3 Ammonia-Hydrogen Exchange Towers Ammonia-hydrogen exchange towers greater than or equal to 35 m (114,3 ft) in height with diameters of 1,5 m (4,9 ft) to 2,5 m (8,2 ft) capable of operating at pressures greater than 15 MPa (2 225 psi) especially designed or prepared for heavy water production utilizing the ammonia-hydrogen exchange process. These towers also have at least one flanged, axial opening of the same diameter as the cylindrical part through which the tower internals can be inserted or withdrawn.

4. Tower internals, including stage contactors, and stage pumps, including those which are submersible, for heavy water production utilizing the ammonia-hydrogen exchange process; TLB6.4 Tower Internals and Stage Pumps Tower internals and stage pumps especially designed or prepared for towers for heavy water production utilizing the ammonia-hydrogen exchange process. Tower internals include especially designed stage contactors which promote intimate gas/liquid contact. Stage pumps include especially designed submersible pumps for circulation of liquid ammonia within a contacting stage internal to the stage towers.

5. Ammonia crackers with operating pressures greater than or equal to 3 MPa for heavy water production utilizing the ammonia-hydrogen exchange process; TLB6.5 Ammonia Crackers Ammonia crackers with operating pressures greater than or equal to 3 MPa (450 psi) especially designed or prepared for heavy water production utilizing the ammoniahydrogen exchange process.

6. Infrared absorption analysers capable of on-line hydrogen/deuterium ratio analysis where deuterium concentrations are equal to or greater than 90 %; TLB6.6 Infrared Absorption Analyzers Infrared absorption analyzers capable of “on-line” hydrogen/deuterium ratio analysis where deuterium concentrations are equal to or greater than 90 %.

7. Catalytic burners for the conversion of enriched deuterium gas into heavy water utilizing the ammonia-hydrogen exchange process; TLB6.7 Catalytic Burners Catalytic burners for the conversion of enriched deuterium gas into heavy water especially designed or prepared for heavy water production utilizing the ammoniahydrogen exchange process.

8. Complete heavy water upgrade systems, or columns therefor, for the upgrade of heavy water to reactor-grade deuterium concentration; TLB6.8 Complete heavy water upgrade systems or columns therefor Complete heavy water upgrade systems, or columns therefor, especially designed or prepared for the upgrade of heavy water to reactor-grade deuterium concentration. EXPLANATORY NOTE These systems, which usually employ water distillation to separate heavy water from light water, are especially designed or prepared to produce reactor-grade heavy water (i.e., typically 99,75 % deuterium oxide) from heavy water feedstock of lesser concentration.

9. Ammonia synthesis converters or synthesis units specially designed or prepared for heavy water production utilizing the ammonia-hydrogen exchange process TLB6.9 Ammonia synthesis converters or synthesis units Ammonia synthesis converters or synthesis units especially designed or prepared for heavy water production utilizing the ammonia-hydrogen exchange process. EXPLANATORY NOTE These converters or units take synthesis gas (nitrogen and hydrogen) from an ammonia/hydrogen high-pressure exchange column (or columns), and the synthesized ammonia is returned to the exchange column (or columns).

0B005 Plant specially designed for the fabrication of “nuclear reactor” fuel elements and specially designed or prepared equipment therefor. Technical Note: Specially designed or prepared equipment for the fabrication of “nuclear reactor” fuel elements includes equipment which: 1. Normally comes into direct contact with or directly processes or controls the production flow of nuclear materials; 2. Seals the nuclear materials within the cladding; 3. Checks the integrity of the cladding or the seal; 4. Checks the finish treatment of the sealed fuel; or 5. Is used for assembling reactor elements. Plants for the fabrication of nuclear reactor fuel elements, and equipment especially designed or prepared therefor INTRODUCTORY NOTE Nuclear fuel elements are manufactured from one or more of the source or special fissionable materials mentioned in MATERIAL AND EQUIPMENT of this annex. For oxide fuels, the most common type of fuel, equipment for pressing pellets, sintering, grinding and grading will be present. Mixed oxide fuels are handled in glove boxes (or equivalent containment) until they are sealed in the cladding. In all cases, the fuel is hermetically sealed inside a suitable cladding which is designed to be the primary envelope encasing the fuel so as to provide suitable performance and safety during reactor operation. Also, in all cases, precise control of processes, procedures and equipment to extremely high standards is necessary in order to ensure predictable and safe fuel performance. EXPLANATORY NOTE Items of equipment that are considered to fall within the meaning of the phrase “and equipment especially designed or prepared” for the fabrication of fuel elements include equipment which: (a) normally comes in direct contact with, or directly processes, or controls, the production flow of nuclear material; (b) seals the nuclear material within the cladding; (c) checks the integrity of the cladding or the seal; (d) checks the finish treatment of the sealed fuel; or (e) is used for assembling reactor fuel elements. Such equipment or systems of equipment may include, for example: 1) fully automatic pellet inspection stations especially designed or prepared for checking final dimensions and surface defects of the fuel pellets; 2) automatic welding machines especially designed or prepared for welding end caps onto the fuel pins (or rods); 3) automatic test and inspection stations especially designed or prepared for checking the integrity of completed fuel pins (or rods); 4) systems especially designed or prepared to manufacture nuclear fuel cladding. Item 3 typically includes equipment for: a) x-ray examination of pin (or rod) end cap welds, b) helium leak detection from pressurized pins (or rods), and c) gamma-ray scanning of the pins (or rods) to check for correct loading of the fuel pellets inside.

0B006 Plant for the reprocessing of irradiated “nuclear reactor” fuel elements, and specially designed or prepared equipment and components therefor. Note: 0B006 includes: a. Plant for the reprocessing of irradiated “nuclear reactor” fuel elements including equipment and components which normally come into direct contact with and directly control the irradiated fuel and the major nuclear material and fission product processing streams; TLB3 Plants for the reprocessing of irradiated fuel elements, and equipment especially designed or prepared therefor INTRODUCTORY NOTE Reprocessing irradiated nuclear fuel separates plutonium and uranium from intensely radioactive fission products and other transuranic elements. Different technical processes can accomplish this separation. However, over the years Purex has become the most commonly used and accepted process. Purex involves the dissolution of irradiated nuclear fuel in nitric acid, followed by separation of the uranium, plutonium, and fission products by solvent extraction using a mixture of tributyl phosphate in an organic diluent. Purex facilities have process functions similar to each other, including: irradiated fuel element chopping, fuel dissolution, solvent extraction, and process liquor storage. There may also be equipment for thermal denitration of uranium nitrate, conversion of plutonium nitrate to oxide or metal, and treatment of fission product waste liquor to a form suitable for long term storage or disposal. However, the specific type and configuration of the equipment performing these functions may differ between Purex facilities for several reasons, including the type and quantity of irradiated nuclear fuel to be reprocessed and the intended disposition of the recovered materials, and the safety and maintenance philosophy incorporated into the design of the facility. A “plant for the reprocessing of irradiated fuel elements”, includes the equipment and components which normally come in direct contact with and directly control the irradiated fuel and the major nuclear material and fission product processing streams. These processes, including the complete systems for plutonium conversion and plutonium metal production, may be identified by the measures taken to avoid criticality (e.g. by geometry), radiation exposure (e.g. by shielding), and toxicity hazards (e.g. by containment).

b. Fuel element chopping or shredding machines, i.e. remotely operated equipment to cut, chop or shear irradiated “nuclear reactor” fuel assemblies, bundles or rods; TLB3.1 Irradiated fuel element chopping machines Remotely operated equipment especially designed or prepared for use in a reprocessing plant as identified above and intended to cut, chop or shear irradiated nuclear fuel assemblies, bundles or rods. EXPLANATORY NOTE This equipment breaches the cladding of the fuel to expose the irradiated nuclear material to dissolution. Especially designed metal cutting shears are the most commonly employed, although advanced equipment, such as lasers, may be used.

c. Dissolvers, critically safe tanks (e.g. small diameter, annular or slab tanks) specially designed or prepared for the dissolution of irradiated “nuclear reactor” fuel, which are capable of withstanding hot, highly corrosive liquids, and which can be remotely loaded and maintained; TLB3.2 Dissolvers Critically safe tanks (e.g. small diameter, annular or slab tanks) especially designed or prepared for use in a reprocessing plant as identified above, intended for dissolution of irradiated nuclear fuel and which are capable of withstanding hot, highly corrosive liquid, and which can be remotely loaded and maintained. EXPLANATORY NOTE Dissolvers normally receive the chopped-up spent fuel. In these critically safe vessels, the irradiated nuclear material is dissolved in nitric acid and the remaining hulls removed from the process stream.

d. Solvent extractors, such as packed or pulsed columns, mixer settlers or centrifugal contractors, resistant to the corrosive effects of nitric acid and specially designed or prepared for use in a plant for the reprocessing of irradiated “natural uranium”, “depleted uranium” or “special fissile materials”; TLB3.3 Solvent extractors and solvent extraction equipment Especially designed or prepared solvent extractors such as packed or pulse columns, mixer settlers or centrifugal contactors for use in a plant for the reprocessing of irradiated fuel. Solvent extractors must be resistant to the corrosive effect of nitric acid. Solvent extractors are normally fabricated to extremely high standards (including special welding and inspection and quality assurance and quality control techniques) out of low carbon stainless steels, titanium, zirconium, or other high quality materials. EXPLANATORY NOTE Solvent extractors both receive the solution of irradiated fuel from the dissolvers and the organic solution which separates the uranium, plutonium, and fission products. Solvent extraction equipment is normally designed to meet strict operating parameters, such as long operating lifetimes with no maintenance requirements or adaptability to easy replacement, simplicity of operation and control, and flexibility for variations in process conditions.

e. Holding or storage vessels specially designed to be critically safe and resistant to the corrosive effects of nitric acid; Technical Note: Holding or storage vessels may have the following features: 1. Walls or internal structures with a boron equivalent (calculated for all constituent elements as defined in the note to 0C004) of at least two per cent; 2. A maximum diameter of 175 mm for cylindrical vessels; or 3. A maximum width of 75 mm for either a slab or annular vessel. TLB3.4 Chemical holding or storage vessels Especially designed or prepared holding or storage vessels for use in a plant for the reprocessing of irradiated fuel. The holding or storage vessels must be resistant to the corrosive effect of nitric acid. The holding or storage vessels are normally fabricated of materials such as low carbon stainless steels, titanium or zirconium, or other high quality materials. Holding or storage vessels may be designed for remote operation and maintenance and may have the following features for control of nuclear criticality: (1) walls or internal structures with a boron equivalent of at least two per cent, or (2) a maximum diameter of 175 mm (7 in) for cylindrical vessels, or (3) a maximum width of 75 mm (3 in) for either a slab or annular vessel. EXPLANATORY NOTE Three main process liquor streams result from the solvent extraction step. Holding or storage vessels are used in the further processing of all three streams, as follows: (a) The pure uranium nitrate solution is concentrated by evaporation and passed to a denitration process where it is converted to uranium oxide. This oxide is re-used in the nuclear fuel cycle. (b) The intensely radioactive fission products solution is normally concentrated by evaporation and stored as a liquor concentrate. This concentrate may be subsequently evaporated and converted to a form suitable for storage or disposal. (c) The pure plutonium nitrate solution is concentrated and stored pending its transfer to further process steps. In particular, holding or storage vessels for plutonium solutions are designed to avoid criticality problems resulting from changes in concentration and form of this stream.

f. Neutron measurement systems specially designed or prepared for integration and use with automated process control systems in a plant for the reprocessing of irradiated “natural uranium”, “depleted uranium” or “special fissile materials”. TLB3.5 Neutron measurement systems for process control Neutron measurement systems especially designed or prepared for integration and use with automated process control systems in a plant for the reprocessing of irradiated fuel elements. EXPLANATORY NOTE These systems involve the capability of active and passive neutron measurement and discrimination in order to determine the fissile material quantity and composition. The complete system is composed of a neutron generator, a neutron detector, amplifiers, and signal processing electronics. The scope of this entry does not include neutron detection and measurement instruments that are designed for nuclear material accountancy and safeguarding or any other application not related to integration and use with automated process control systems in a plant for the reprocessing of irradiated fuel elements.

0B007 Plant for the conversion of plutonium and equipment specially designed or prepared therefor, as follows: TLB7.2.1 Especially designed or prepared systems for the conversion of plutonium nitrate to oxide

0B007.a a. Systems for the conversion of plutonium nitrate to oxide; EXPLANATORY NOTE The main functions involved in this process are: process feed storage and adjustment, precipitation and solid/liquor separation, calcination, product handling, ventilation, waste management, and process control. The process systems are particularly adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards. In most reprocessing facilities, this process involves the conversion of plutonium nitrate to plutonium dioxide. Other processes can involve the precipitation of plutonium oxalate or plutonium peroxide.

0B007.b b. Systems for plutonium metal production. TLB7.2.2 Especially designed or prepared systems for plutonium metal production EXPLANATORY NOTE This process usually involves the fluorination of plutonium dioxide, normally with highly corrosive hydrogen fluoride, to produce plutonium fluoride which is subsequently reduced using high purity calcium metal to produce metallic plutonium and a calcium fluoride slag. The main functions involved in this process are fluorination (e.g. involving equipment fabricated or lined with a precious metal), metal reduction (e.g. employing ceramic crucibles), slag recovery, product handling, ventilation, waste management and process control. The process systems are particularly adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards. Other processes include the fluorination of plutonium oxalate or plutonium peroxide followed by a reduction to metal.

0C001 “Natural uranium” or “depleted uranium” or thorium in the form of metal, alloy, chemical compound or concentrate and any other material containing one or more of the foregoing; Note: 0C001 does not control the following: a. Four grammes or less of “natural uranium” or “depleted uranium” when contained in a sensing component in instruments; b. “Depleted uranium” specially fabricated for the following civil non-nuclear applications: 1. Shielding; 2. Packaging; 3. Ballasts having a mass not greater than 100 kg; 4. Counter-weights having a mass not greater than 100 kg; c. Alloys containing less than 5 % thorium; d. Ceramic products containing thorium, which have been manufactured for non-nuclear use. TLA.1.1 1.1. “Source material” The term “source material” means uranium containing the mixture of isotopes occurring in nature; uranium depleted in the isotope 235; thorium; any of the foregoing in the form of metal, alloy, chemical compound, or concentrate; any other material containing one or more of the foregoing in such concentration as the Board of Governors shall from time to time determine; and such other material as the Board of Governors shall from time to time determine.

0C002 “Special fissile materials” Note: 0C002 does not control four “effective grammes” or less when contained in a sensing component in instruments. TLA.1.2 1.2. “Special fissionable material” i) The term “special fissionable material” means plutonium-239; uranium-233; “uranium enriched in the isotopes 235 or 233”; any material containing one or more of the foregoing; and such other fissionable material as the Board of Governors shall from time to time determine; but the term “special fissionable material” does not include source material. ii) The term “uranium enriched in the isotopes 235 or 233” means uranium containing the isotopes 235 or 233 or both in an amount such that the abundance ratio of the sum of these isotopes to the isotope 238 is greater than the ratio of the isotope 235 to the isotope 238 occurring in nature. However, for the purposes of the Guidelines, items specified in subparagraph (a) below, and exports of source or special fissionable material to a given recipient country, within a period of 12 months, below the limits specified in subparagraph (b) below, shall not be included: (a) Plutonium with an isotopic concentration of plutonium-238 exceeding 80 %. Special fissionable material when used in gram quantities or less as a sensing component in instruments; and Source material which the Government is satisfied is to be used only in non-nuclear activities, such as the production of alloys or ceramics; (b) Special fissionable material 50 effective grams; Natural uranium 500 kilograms; Depleted uranium 1 000 kilograms; and Thorium 1 000 kilograms.

0C003 Deuterium, heavy water (deuterium oxide) and other compounds of deuterium, and mixtures and solutions containing deuterium, in which the isotopic ratio of deuterium to hydrogen exceeds 1:5 000 . TLB2.1 2.1. Deuterium and heavy water Deuterium, heavy water (deuterium oxide) and any other deuterium compound in which the ratio of deuterium to hydrogen atoms exceeds 1:5 000 for use in a nuclear reactor as defined in paragraph 1.1. above in quantities exceeding 200 kg of deuterium atoms for any one recipient country in any period of 12 months.

0C004 Graphite having a purity level better than 5 parts per million ‘boron equivalent’ and with a density greater than 1,50 g/cm3 for use in a “nuclear reactor”, in quantities exceeding 1 kg. N.B.: SEE ALSO 1C107 Note 1: For the purpose of export control, the competent authorities of the Member State in which the exporter is established will determine whether or not the exports of graphite meeting the above specifications are for “nuclear reactor” use. Note 2: In 0C004, ‘boron equivalent’ (BE) is defined as the sum of BE z for impurities (excluding BE carbon since carbon is not considered an impurity) including boron, where: BEZ (ppm) = CF × concentration of element Z in ppm; and σB and σZ are the thermal neutron capture cross sections (in barns) for naturally occurring boron and element Z respectively; and AB and AZ are the atomic masses of naturally occurring boron and element Z respectively. TLB2.2 2.2. Nuclear grade graphite Graphite having a purity level better than 5 parts per million boron equivalent and with a density greater than 1,50 g/cm3 for use in a nuclear reactor as defined in paragraph 1.1 above, in quantities exceeding 1 kilogram. EXPLANATORY NOTE For the purpose of export control, the Government will determine whether or not the exports of graphite meeting the above specifications are for nuclear reactor use. Boron equivalent (BE) may be determined xperimentally or is calculated as the sum of BEz for impurities (excluding BEcarbon since carbon is not considered an impurity) including boron, where: BEZ (ppm) = CF × concentration of element Z (in ppm); CF is the conversion factor: (σZ × AB) divided by (σB × Az); σB and σZ are the thermal neutron capture cross sections (in barns) for naturally occurring boron and element Z respectively; and AB and Az are the atomic masses of naturally occurring boron and element Z respectively.

0C005 Specially prepared compounds or powders for the manufacture of gaseous diffusion barriers, resistant to corrosion by UF6 (e.g. nickel or alloy containing 60 weight per cent or more nickel, aluminium oxide and fully fluorinated hydrocarbon polymers), having a purity of 99,9 % by weight or more and a particle size less than 10 μm measured by American Society for Testing and Materials (ASTM) B330 standard and a high degree of particle size uniformity. TLB5.3.1b Gaseous diffusion barriers and barrier materials (b) especially prepared compounds or powders for the manufacture of such filters. Such compounds and powders include nickel or alloys containing 60 % or more nickel, aluminium oxide, or UF6-resistant fully fluorinated hydrocarbon polymers having a purity of 99,9 % by weight or more, a particle size less than 10 μm, and a high degree of particle size uniformity, which are es