1. ------IND- 2016 0296 CZ - EN- ------ 20160712 --- --- PROJET 
 
II. 
Draft  
 
DECREE  
of … 2016  
 
on selected nuclear items  
The State Office for Nuclear Safety stipulates, pursuant to §  236 of Act No  .../...., the Atomic 
Act, toward s the implementation of §  18(5), § 24(7), §  25(2)(d), §  166(6)(d), and §  169(4):  
§ 1 
The list of selected nuclear items  
The list of selected nuclear items is stipulated by Annex  1 to this decree.  
§ 2 
Sample end -user declaration  
The sample declar ation of an end -user of a selected nuclear item during its import is 
stipulated by Annex  2 to this decree.  
§ 3 
The scope and retention method and period for registered data on nuclear items that are 
selected nuclear items and deadlines for providing data to the office  
(1) In the case of export, import or transit of a selected nuclear item, the following 
information must be recorded:  
a) the amount, name, and specifications of the selected nuclear item in accordance with this 
decree;  
b) the name and  address of the supplier and end -user of the selected nuclear item, if they are 
corporate subjects, or their name(s) and surname and permanent address, if they are 
natural persons;  
c) the proposal to conclude a contract and other commercial documents;  
d) the dat e the import, export or transit will occur;  
e) the date when the imported, exported or transited nuclear item entered the Czech 
Republic or left the Czech Republic;  
f) in the case of import, when the selected item was delivered to the end -user; and  
g) written confi rmation from the end -user regarding acceptance of the selected nuclear item.  
(2) The holder of a permit for the export, import or transit of a selected nuclear item must 
furnish the office the information pursuant to (1)  
a) (a) to (f) within 5  workdays of the com pletion of export, import or transit; and  
b) (g) within 30  days of the selected nuclear item having been delivered to the end -user.  
(3) The holder of a permit for the export, import or transit of a selected nuclear item shall 
archive the recorded information for at least 3  years from their origin.   - 2 - 
CELEX: 21999A0313(01)  
§ 4 
The particulars of the end -use statement for nuclear items that are selected nuclear 
items  
The end -use statement for nuclear items in case of their transfer must contain:  
a) the amount, name, and specifications of the selected nuclear item in accordance with this 
decree;  
b) information regarding end  use; 
c) the transfer date;  
d) information regarding the notifying party, as follows;  
1. their name(s) and surname in the case of a natural perso n; or 
2. their name in the case of a corporate subject;  
e) the end -user's registered offices or permanent address;  
f) a pledge by the end -user 
1. to not use the selected nuclear item or part thereof for any purposes contrary to the 
Treaty on the Non -Proliferation of N uclear Weapons;  
2. to ensure notification of further transfer of the selected nuclear item or part thereof 
within the Czech Republic;  
3. to ensure notification of further transfer of the selected nuclear item or part thereof 
within the Czech Republic; and  
g) the ex pected date the office shall be notified of information on the completed transfer, 
which shall follow within 30  days of the transfer having been completed.  
§ 5 
Content requirements for documentation for import, export or transit of nucl ear items 
that are selected nuclear items  
Documentation for authorised activity that is the import, export or transit of a selected 
nuclear item is a set of information similar to the information pursuant to §  3(1)(a) to (d).  
CELEX: 21999A0313(01)  
§ 6 
Notification  
This decree was notified in accordance with Directive (EU)  2015/1535 of the European 
Parliament and of the Council of 9  September  2015 laying down a procedure for the provision 
of information in the field of technical regulatio ns and of rules on information society 
services.  
 
 
 
Chair:   - 3 - 
Annex  1 to Decree  No .../... 
THE LIST OF SELECTED NUCLEAR ITEMS SUBJECT TO CONTROLS DURING 
IMPORT, EXPORT, TRANSIT, AND TRANSFER  
(SELECTED NUCLEAR MATERIALS, EQUIPMENT AND TECHNOLOGY)  
1. Nuclear react ors and specially designed or prepared equipment and components for 
their operation  
Various types of nuclear reactors according to moderator type (e.g. graphite, heavy water, 
light water, no moderator), neutron spectrum (e.g. thermal, fast), coolant type ( e.g. water, 
liquid metal, molten salt, gas), function, or type (e.g. power reactors, research reactors, test 
reactors).  
All items in point  1 include all of the listed nuclear reactor types. Point  1 does not include 
fusion reactors.  
1.1. Complete nuclear reactor s 
Nuclear reactors capable of sustaining a controlled fission chain reaction.  
‘Nuclear reactor’ includes items that are located within a reactor vessel or that are directly 
connected to it, equipment that manages core output, and components that contain th e coolant 
of the primary circuit of reactor, come into direct contact with it, or control its circulation.  
1.2. Reactor vessels  
Metal vessels or major shop -fabricated parts specially designed or prepared for location in the 
core of a nuclear reactor as specifie d in Item  1.1, and nuclear reactor internals as defined in 
Item 1.8. 
Item 1.2 applies to reactor vessels regardless of rated pressure, and includes reactor pressure 
vessels and heavy water reactor vessels.  
The lid of the reactor vessel is included in Item  1.2 as a major shop -produced component of 
the reactor vessel.  
1.3. Refuelling machines for nuclear reactors  
Handling equipment, specially designed or prepared for inserting or removing nuclear fuel 
from a nuclear reactor as specified in Item  1.1, capable of rep lacing nuclear fuel during 
operation or of using technically complex elements for placing or orienting that permit the 
performance of a set of operations taking place during the replacement of nuclear fuel during 
nuclear reactor shutdown, when direct obser vation or access to nuclear fuel are usually not 
possible.  
1.4. Nuclear reactor control rods and related equipment  
Specially constructed or prepared rods, their load -bearing or suspensive structures, traction 
bars and guide tubes for managing the fission proces s in a nuclear reactor as specified in 
Item 1.1. 
1.5. Nuclear reactor pressure tubes  
Tubes that are specially designed or prepared to accept fuel elements and the primary cooling 
medium of a nuclear reactor as specified in Item  1.1. Pressure tubes are part of f uel channels 
designed for operation under high pressure, which may exceed 5  MPa.  
1.6. Nuclear fuel cladding  
Zirconium tubes or zircon alloy tubes (or tube systems), specially designed or prepared for 
use as cladding of nuclear fuel in a nuclear reactor as speci fied in Item  1.1, in amounts in 
excess of 10  kg. 
Zirconium pressure tubes are classified under Item  1.5; tubes for heavy  water reactor vessels 
are classified under Item  1.8.  - 4 - 
Metal tubes made of zirconium or zirconium alloys intended for use in nuclear reac tors have a 
hafnium to zirconium weight ratio that is typically less than 1:500.  
1.7. Primary coolant pumps or circulators  
Pumps or circulators that are specially designed or prepared to ensure the circulation of the 
primary cooling medium of a nuclear reactor as specified in Item  1.1. Specially designed or 
prepared pumps or circulators include pumps for water -cooled reactors, circulators for gas -
cooled reactors  and electromagnetic or mechanical pumps for liquid metal -cooled nuclear 
reactors.  
Legend : 
These devic es may include pumps with elaborate sealed or multi -sealed systems to prevent leakage of primary 
coolant, canned motor pumps  and pumps with inertial mass systems.  
These devices include pumps certified in accordance with Part  III Section  I Subsection  NB (pa rt of Class  1) of 
the American Society of Mechanical Engineers (ASME) Code, or equivalent standards.  
1.8. Nuclear reactor internals  
Nuclear reactor internals specially designed or prepared for use in a nuclear reactor as 
specified in Item  1.1. Item  1.8, for exa mple, includes load -bearing core structures, fuel 
channels, heavy water reactor vessel tubes, thermal shields, baffles, core grid plates  and 
diffuser plates.  
Nuclear reactor internals are defined as important structures within a reactor vessel, which 
have one or more functions such as supporting the core, maintaining fuel alignment, directing 
the flow of primary coolant, providing radiation shielding for the reactor vessel and guiding 
in-core instrumentation.  
1.9. Heat exchangers  
1.9.1.  Steam generators specially desig ned or prepared for use in the primary or 
inserted cooling circuit of a nuclear reactor as specified in Item  1.1. 
1.9.2.  Other heat exchangers specially designed or prepared for use in the primary 
cooling circuit of a nuclear reactor as specified in Item  1.1. 
Steam generators are specially designed or prepared equipment for transferring heat generated 
in a nuclear reactor to feed water for steam generation. In the case of a fast reactor that uses a 
coolant loop as an intermediate stage, the steam generator is in t he inserted circuit.  
In the case of a gas -cooled nuclear reactor, the heat exchanger can be used to transfer heat to a 
secondary gas loop that powers a gas turbine. This item does not include heat exchangers in 
reactor support systems such as emergency aft er-cooling systems or decay heat -cooling 
systems.  
1.10. Neutron detectors  
Specially designed or prepared neutron detectors for measuring the neutron flux in the core of 
a nuclear reactor as specified in Item  1.1. 
This item includes internal and external devices that measure neutron flux levels over a large 
range, usually from 104 neutrons per  cm2/s to 1010 neutrons per  cm2/s or more.  
Detectors outside a reactor core include devices outside the core of a nuclear reactor as 
specified in Item  1.1, which are however located within the biological shielding.  
1.11. External thermal shielding  
External thermal shields specially designed or prepared for use in a nuclear reactor as 
specified in Item  1.1. to reduce heat losses and to protect the containment vessel.  
External thermal  shields are important structures placed over the reactor vessel that reduce a 
nuclear reactor's heat loss and lower the temperature inside the containment vessel.  
 
2. Non-nuclear materials for reactors  
2.1. Deuterium and heavy water  
Deuterium, heavy water (deuter ium oxide) and other compounds of deuterium, in which the 
ratio of deuterium atoms to hydrogen atoms exceeds 1:5  000 for use in a nuclear reactor as  - 5 - 
specified in Item  1.1, in quantities exceeding 200  kg of deuterium for any one recipient 
country in any per iod of 12  months.  
2.2. Nuclear grade graphite  
Graphite with a purity of more than 5  parts per million boron equivalent and density greater 
than 1.5  g/cm3 that is suitable for use in a nuclear reactor listed in Item  1.1, in quantities 
exceeding 1  kg for any one recipient country in any period of 12  months. The boron 
equivalent (BE) may be determined experimentally or calculated as the sum BE z for 
impurities (other than BE carbon, since carbon is not considered to be an impurity) including 
boron, where: BE z (ppm) =  CF x the concentration of element Z (in ppm), CF is a conversion 
factor defined as follows:  
 
 
 
where δB a δZ are the effective thermal neutron capture cross -sections (in barns) for naturally -
occurring boron and element Z respectively; and A B a A Z are the atomic masses of naturally -
occurring boron and element Z respectively Z.  
 
3. Plants for the reprocessing of irradiated fuel elements and equipment specially 
designed or prepared for this purpose  
Plants for the reprocessing of irradiated fuel elements or parts thereof, which are defined as 
equipment for chopping irradiated fuel elements, dissolving nuclear fue l, liquid extraction  and 
storage of process solutions. Plants may also contain equipment for thermal denitrification of 
uranium nitrate, conversion of plutonium nitrate to oxide or metal, and for treatment of fission 
product waste liquor into a form that i s suitable for long -term storage or disposal.  
Items corresponding to the term ‘equipment specially designed or prepared for reprocessing 
irradiated fuel elements’ include:  
3.1. Machines for chopping irradiated fuel elements  
Remotely operated equipment specially  designed or prepared for use in the plant for 
reprocessing irradiated fuel elements, which are intended for cutting, chopping or shearing 
irradiated fuel assemblies, bundles or rods. This equipment breaches the cladding of the 
nuclear fuel and thus prepar es the irradiated nuclear material for dissolution. Specially 
designed mechanical shears are most commonly used, but other equipment such as lasers may 
also be used.  
3.2. Solvent tanks  
Tanks secured against criticality (for example, a small diameter, annular, o r slab design), 
specially designed or prepared for use in irradiated fuel element reprocessing plants, which 
are intended for dissolution of irradiated nuclear fuel in nitric acid and which are resistant to 
hot, highly corrosive liquid and can be remotely loaded and serviced.  
Solvent tanks normally hold chopped -up irradiated nuclear fuel. In these vessels, secured 
against criticality, the irradiated nuclear material is dissolved in nitric acid and the remaining 
non-soluble parts are removed from the process  stream.  
3.3. Liquid extractors and liquid extraction equipment  
Specially designed or prepared extractors such as packed and pulse columns, mixing and 
settling tanks or centrifugal reactors, intended for use in plants for the reprocessing of 
irradiated fuel ele ments. Liquid extractors must be resistant to corrosion by nitric acid.  
Liquid extractors are normally produced under extremely high standards (including special 
welding, inspections, quality assurance and quality control) of low carbon stainless steel, 
titanium, zirconium and other high -quality materials.   - 6 - 
Liquid extractors hold a solution of irradiated nuclear fuel from solvent tanks and organic 
solutions for the separation of uranium, plutonium  and fission products. Equipment for liquid 
extraction is usua lly designed to meet strict operating parameters, such as a long operating life 
without maintenance requirements, easy replacement, simplicity of operation and control, and 
flexibility under variable operating conditions.  
3.4. Chemical holding or storage vessel s 
Specially designed or prepared holding or storage vessels intended for use in a plant for the 
reprocessing of irradiated nuclear fuel. These holding or storage vessels must be resistant to 
corrosion by nitric acid. They are usually manufactured from stai nless steel, titanium, 
zirconium  and other high -quality materials. Holding or storage vessels may be designed for 
remote control and maintenance and may have the following parameters in order to prevent 
criticality: walls or internal structures correspondi ng to a boron equivalent of at least 2  % or a 
maximum diameter of 175  mm for cylindrical vessels, or a maximum width of 75  mm for 
every slab or annular vessel.  
Chemical holding or storage vessels are used for further processing of three main flows 
exiting the extraction operation: the pure nitric acid solution is concentrated through 
evaporation, and during the subsequent denitrification process is transformed to uranium 
oxide, where it is re -used in the nuclear fuel cycle. The highly radioactive fission pr oducts 
solution is normally concentrated by evaporation and stored as a liquid concentrate. This 
concentrate may be subsequently evaporated and converted to a form suitable for storage or 
disposal. The pure plutonium nitrate solution is concentrated and st ored until it is transformed 
for further process steps. Special holding or storage vessels for plutonium solutions are 
designed to prevent criticality problems caused by changes in the concentration and form of 
this solution.  
3.5. Neutron measurement systems fo r process control  
Neutron measurement systems specially designed or prepared for integration and use with 
automatic process control systems in plants for the reprocessing of irradiated fuel elements. 
These systems are capable of active and passive neutron measurement and discriminatory 
ability to stipulate the amount and mix of fissile materials. The system comprises a neutron 
generator, a neutron detector, amplifiers  and signal processing electronics.  
This item does not include neutron detection and measur ement devices designed for warranty 
purposes for nuclear materials accountancy, or other applications that do not apply to 
integration or use with automatic process control systems in plants for the reprocessing of 
irradiated fuel elements.  
 
4. Plants for the  fabrication of nuclear reactor fuel elements and equipment specially 
designed or prepared for this purpose  
Plants for the fabrication of oxide -based fuel elements and parts thereof, which are facilities 
for pressing tablets, sintering, crushing, and sorti ng and plants for the fabrication of MOX 
type nuclear fuel. This item includes equipment that comes into direct contact with nuclear 
materials, directly processes or checks the production flow of nuclear material, hermetically 
seals nuclear material within  the scope of cladding, checks the integrity of cladding and 
hermetic seals, checks the final finish of hermetically sealed nuclear fuel, or is used to 
complete fuel elements for nuclear reactors.  
Items corresponding to 'equipment specially designed or pre pared for fabrication of fuel 
elements' include, for example, fully automated inspection stends specially designed or 
prepared for checking the final dimensions and surface defects of tablets, automatic welding 
machines specially designed or prepared for w elding end covers of fuel elements (or rods), 
systems specially designed or prepared for fabricating nuclear fuel cladding, and automatic 
testing and inspection stends specially designed or prepared to check the integrity of  - 7 - 
completed fuel elements (or rod s) – these usually include equipment for X -ray testing of 
welds on elements (or rods), equipment for detecting helium leaks from pressurised elements 
(or rods), and equipment for gamma scanning elements (or rods) in order to verify that they 
have been prop erly filled with fuel pellets.  
 
5. Plants for the separation of isotopes of natural uranium, depleted uranium or special 
fissionable material, and equipment other than analytical instruments specially 
designed or prepared for this purpose  
Plants, equipment, a nd technology for uranium isotope separation, and plants, equipment and 
technology for the separation of isotopes of other elements, except for plants, equipment and 
technology for the separation of isotopes of other elements utilising an electromagnetic 
separation process.  
Items that correspond to the term ‘equipment, other than analytical instruments, specially 
designed or prepared for the separation of isotopes of uranium’ include:  
5.1. Gas centrifuges, assemblies  and components specially designed or prepared  for 
use in gas centrifuges  
Gas centrifuges consisting of a thin -walled cylinder with a diameter of 75  mm to 650  mm 
placed in a vacuum and spun at high peripheral speed on the order of 300  m/s or more, around 
a vertical axis. Rotary component structural ma terials must have a high strength to density 
ratio in order to achieve the desired speed. The rotor assembly, and therefore its individual 
components, must be manufactured to very close tolerances in order to minimise imbalances 
during operation. A gas cen trifuge for uranium enrichment is characterised by having within 
the rotor chamber a rotating disc baffle and a stationary tube arrangement for feeding tube and 
extracting UF 6 gas and featuring at least three separate channels, two of which are connected 
to scoops extending from the rotor axis towards the periphery of the rotor chamber. 
Components also include critical non -rotating parts that, though they are specially designed, 
are not made of special materials.  
5.1.1.  Rotating components  
5.1.1.1.  Complete rotor assemblie s 
Thin -walled cylinders or a number of interconnected thin -walled cylinders, which are made 
from one or more of the materials with a high strength to density ratio. If the cylinders are 
interconnected, they are connected by flexible bellows or rings as des cribed in Item  5.1.1.3. 
The rotor is equipped with an internal deflector and end caps described in Item  5.1.1.4 and 
Item 5.1.1.5. The complete assembly may be delivered only partly assembled.  
5.1.1.2.  Rotor tubes  
Specially designed or prepared thin -walled cylinders  with a wall thickness of 12  mm or less, 
with a diameter of 75  mm to 650  mm made from a material with a high strength to density 
ratio.  
5.1.1.3.  Rings or bellows  
Components specially designed or prepared that allow placement of a support to the rotor tube 
or to joi n together a number of rotor tubes. Bellows are a coiled short cylinder with a diameter 
of 75  mm to 650  mm with a maximum wall thickness of 3  mm, made of a material with high 
strength to density ratio.  
5.1.1.4.  Baffles (deflectors)  
Disc-shaped components with a dia meter of 75  mm to 650  mm, specially designed or 
prepared to be fitted 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 circulation of UF 6 gas 
inside the main separa tion chamber of the rotor tube. They are made from a material with high 
strength to density ratio.   - 8 - 
5.1.1.5.  Top and bottom end caps  
Disc-shaped components with a diameter of 75  mm to 650  mm specially designed or prepared 
to fit the ends of the rotor tube and contai n the UF 6 within the rotor tube, and in some cases to 
support, retain or contain as an integral part an element of the upper bearing (top cap), or to 
carry the rotating elements of the motor and lower bearing (bottom cap). They are made from 
a material wit h high strength to density ratio.  
For rotation parts of centrifuges as described in Item  5.1.1.1 to 5.1.1.5, high -strength steel is 
used, having an ultimate tensile strength of 1.95  GPa or greater; aluminium alloys having an 
ultimate tensile strength of 0. 46 GPa or greater; or fibrous materials suitable for use in 
composite structures with a specific modulus of 3.18  x 106 m or greater and an ultimate 
tensile strength of 7.62  x 104 m or greater (the ‘specific modulus’ is Young's modulus in  N/m2 
divided by th e specific mass in N/m3; the ‘specific ultimate tensile strength’ is the ultimate 
tensile strength in  N/m2 divided by the specific mass in  N/m3). 
5.1.2.  Static components  
5.1.2.1.  Magnetic suspension bearings  
5.1.2.1.1.  Specially designed or prepared bearing assemblies, consisting o f 
annular magnets suspended within a housing containing a damping medium. The housing is 
made of material resistant to UF 6, which for this item is defined as copper, copper alloys, 
stainless steel, aluminium, aluminium oxide, aluminium alloys, nickel or it s alloys with at 
least 60  % nickel content, and fluoropolymers. Magnetic couples with a pole piece or a 
second magnet are attached to the top cap, as described in Item  5.1.1.5. The magnet may have 
an annular shape, where the maximum ratio of the outside di ameter to the inside diameter is 
1.6:1. The magnet may have an initial permeability of at least 0.15  H/m, a minimum 
remanence of 98.5  % or greater, and an energy product of greater than 80  kJ/m3. Aside from 
the usual material properties, the deviation of t he magnetic axis from the geometric axis is 
limited by very tight tolerances, less than 0.1  mm, or the magnet material is highly 
homogeneous.  
5.1.2.1.2.  Active magnetic bearings specially designed or prepared for use 
with gas centrifuges. These bearings usually have the following characteristics: they are 
designed to maintain centre rotor rotation up to at least 600  Hz, and are connected to a reliable 
power source or backup source (UPS) in order to maintain functionality for over 1  hour.  
5.1.2.2.  Bearings and dampers  
Specially  designed or prepared bearings comprising a pivot or cup mounted on a damper. The 
pivot is usually a hardened steel shaft with a hemisphere at one end and a means of 
attachment to the bottom cap described in Item  5.1.1.5 at the other. The shaft may also ha ve 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.  
5.1.2.3.  Molecular pumps  
Specially designed or prepared cylinders having internally -machined or extruded helical 
grooves and internally -machined bores. The usual dimensions are as follows: inside diameter 
75 mm to 650  mm, wall thickness at least 10  mm, with a length to diameter ration of 1:1 or 
greater. Grooves are typically rectangular in cross -section and 2  mm or more in depth.  
5.1.2.4.  Motor stators  
Specially designed or prepared annular stators for high -speed multiphase AC hysteresis or 
reluctance motors, prepared for synchronous operation within a vacuum in the frequency 
range of 600  Hz or greater and a power of at least 40  VA. Motor stators may consist of 
multiphase windings on a laminated low -loss metal core composed of thin layers, usually 
2 mm thick or less.   - 9 - 
5.1.2.5.  Centrifuge housings  
Components specially designed or prepared for the mounting of a gas cent rifuge rotor tube 
assembly. The housing consists of a rigid cylinder with a wall thickness of up to 30  mm with 
precision machined ends to locate the bearings and with one or more mounting flanges. The 
machined ends are parallel to each other and perpendicu lar to the longitudinal axis of the 
cylinder with a deviation less than or equal to 0.05°. The housing may also be a honeycomb 
type structure to accommodate several rotor tubes.  
5.1.2.6.  Blades  
Specially designed or prepared tubes for the extraction of UF 6 gas from  the rotor tube by pitot 
tube action (with an aperture facing into the circumferential gas flow inside the rotor tube, for 
example, by bending the end of a radially placed tube), which can be fitted to the central gas 
extraction system.  
5.2. Specially designed or prepared auxiliary systems, equipment  and components 
for gas centrifuge enrichment plants  
5.2.1.  Feed systems and systems for removal of ‘products’ and ‘tails’  
Specially designed or prepared process systems or equipment for enrichment plants made of 
or protect ed by materials resistant to corrosion by UF 6. For this item, material resistant to UF 6 
is defined as copper, copper alloys, stainless steel, aluminium, aluminium oxide, aluminium 
alloys, nickel or its alloys containing at least 60  % nickel, and fluoropoly mers.  
5.2.1.1.  Feed autoclaves, ovens  or systems used for passing UF 6 to the 
enrichment process.  
5.2.1.2.  Desublimers, cold traps  or pumps used to eliminate UF 6 from the 
enrichment process for subsequent transport after heating.  
5.2.1.3.  Solidification or liquefaction stations used to remove UF 6 from the 
enrichment process by compression and transformation of UF 6 to a liquid or solid.  
5.2.1.4.  ‘Product’ and ‘tails’ stations used for trapping UF 6 into containers.  
5.2.2.  Machine header piping systems (collectors)  
Specially designed or prepared piping systems and header systems (collectors) for handling 
UF 6 within centrifuge cascades. The piping network is normally a triple header system, where 
each centrifuge is connected to each of the headers (collectors). This arrangement is repeated 
many times. The se systems are constructed of materials resistant to corrosion by UF 6 and 
manufactured such that they meet very high vacuum and cleanliness standards. For this item, 
material resistant to UF 6 is defined as copper, copper alloys, stainless steel, aluminium,  
aluminium oxide, aluminium alloys, nickel or its alloys containing at least 60  % nickel, and 
fluoropolymers.  
5.2.3.  Special shut -off and control valves  
Specially designed or prepared valves include, for example, bellows -sealed valves, rapid -
action flaps  or rapid -action valves.  
5.2.3.1.  Shut-off valves specially designed or prepared for feed, product  or tails 
UF 6 gas flows for individual gas centrifuges.  
5.2.3.2.  Bellows -sealed valves, manual or automatic, shut -off or control, made 
of or protected by materials resistant to corrosio n by UF 6, with inside diameter 10 to 160  mm, 
specially designed or prepared for use in main or auxiliary systems of gas centrifuge 
enrichment plants.  
For this item, material resistant to UF6 is defined as copper, copper alloys, stainless steel, 
aluminium, aluminium oxide, aluminium alloys, nickel or its alloys containing at least 60  % 
nickel, and fluoropolymers.  
5.2.4.  UF 6 analysis mass spectrometers and ion sources  
Specially designed or prepared mass spectrometers capable of on -line sampling from a stream 
of gase ous UF 6 that have:   - 10 - 
5.2.4.1.  the ability to measure ions with an atomic mass of 320 or greater and a 
unit resolution better than 1:320;  
5.2.4.2.  ion sources made of nickel, nickel and copper alloys containing at least 
60 % nickel by weight, or nickel and chrome alloys, or co ated with these materials;  
5.2.4.3.  electron bombardment ionisation sources; and  
5.2.4.4.  a collector system suitable for isotopic analysis.  
5.2.5.  Frequency changes  
Frequency changers (also known as converters or inverters) specially designed or prepared to 
supply motor stators a s described in Item  5.1.2.4, or parts, components, and sub -assemblies of 
such frequency changers having the following characteristics:  
5.2.5.1.  a multiphase frequency output of 600  Hz or more; and  
5.2.5.2.  high stability with frequency control better than 0.2  %; 
5.3. Specially d esigned or prepared assemblies and components for use in gaseous 
diffusion enrichment  
Items corresponding to ‘specially designed or prepared assemblies and components for use in 
gaseous diffusion enrichment’ include:  
5.3.1.  Gas diffusion barriers and barrier mate rials  
5.3.1.1.  Specially designed or prepared thin porous filters with pore size of 10 to 
100 nm, of thickness 5  mm or less, and in the case of a cylindrical shape with a diameter of 
25 mm or less, made of metal, polymer  or ceramic materials, resistant to corrosion  by UF 6, 
which for this item are defined as copper, copper alloys, stainless steel, aluminium, 
aluminium oxide, aluminium alloys, nickel or its alloys containing at least 60  % nickel, and 
fluoropolymers.  
5.3.1.2.  Specially prepared compounds or powders for the prod uction of these 
filters. Such compounds and powders include nickel or its alloys with a minimum of 60  % 
nickel, aluminium oxide  or fully UF 6-resistant fluoropolymers with a purity of 99.9  % or 
more, with a particle size of less than 10-6 m and a high degre e of uniformity of particle size, 
which are specially adapted for the manufacture of gaseous diffusion barriers.  
5.3.2.  Diffuser housings  
Specially designed or prepared hermetically sealed containers with diffusion barriers made of 
or coated with material resista nt to corrosion by UF 6, which for this item is defined as copper, 
copper alloys, stainless steel, aluminium, aluminium oxide, aluminium alloys, nickel or its 
alloys containing at least 60  % nickel, and fluoropolymers.  
5.3.3.  Compressors and gas blowers  
Specially designed or prepared compressors or gas blowers with minimum suction of 
1 m3/min. UF 6 and discharge pressure up to 500  kPa, designed for long -term functionality in 
an environment containing UF 6, as well as individual assemblies of these compressors and gas  
blowers. These compressors and gas blowers have a pressure ratio of 10:1 or less and are 
made of or coated with material resistant to corrosion by UF 6, which for this item is defined 
as copper, copper alloys, stainless steel, aluminium, aluminium oxide, a luminium alloys, 
nickel or its alloys containing at least 60  % nickel, and fluoropolymers.  
5.3.4.  Rotary shaft seals  
Specially designed or prepared vacuum seals, which ensure the sealing of input and output 
flanges, used for sealing the shaft connecting the compr essor rotor or gas blowers with the 
drive motor and providing a reliable seal for the inner chamber of a compressor or gas blower 
that is filled with UF 6. Such seals are normally designed with a buffer gas in -leakage rate of 
less than 1  000 cm3/min.  
5.3.5.  Heat e xchangers for cooling UF 6 
Specially designed or prepared heat exchangers made of or coated with material resistant to 
corrosion by UF 6, which for this item is defined as copper, copper alloys, stainless steel,  - 11 - 
aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing at least 60  % 
nickel, and fluoropolymers. These are designed for a maximum rate of pressure change due to 
leaks of less than 10  Pa per hour at a pressure difference of 100  kPa. 
5.4. Specially designed or prepared auxiliary system s, equipment  and components 
for use in gas diffusion enrichment plants  
The items described below come into direct contact with UF 6 process gas or directly regulate 
flow in the cascade. They meet very high vacuum and cleanliness standards. Measurement, 
regulation  and control systems ensure strict and continuous maintenance of vacuum in all 
technological systems, automatic accident protection  and precise automated regulation of gas 
flow. All surfaces that come into contact with the process gas are made of or protected by 
UF 6-resistant materials.  
5.4.1.  Feed systems and systems for removal of ‘products’ and ‘tails’  
Specially designed or prepared systems or equipment made of or coated with material 
resistant to corrosion by UF 6, which for this item is defined as copper , copper alloys, stainless 
steel, aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing at least 
60 % nickel, and fluoropolymers, including:  
5.4.1.1.  Feed autoclaves, ovens  or systems used for passing UF 6 to the 
enrichment process.  
5.4.1.2.  Desublime rs, cold traps  or pumps used to eliminate UF 6 from the 
enrichment process for subsequent transport after heating.  
5.4.1.3.  Solidification or liquefaction stations used to remove UF 6 from the 
enrichment process by compression and transformation of UF 6 to a liquid or  solid.  
5.4.1.4.  ‘Product’ and ‘tails’ stations used for trapping UF 6 into containers.  
5.4.2.  Header piping systems (collectors)  
Specially designed or prepared piping systems and header systems (collectors) for 
transporting UF 6 within the gaseous diffusion cascades. This piping network is normally 
designed with a double system of headers (collectors), with each unit connected to each of the 
headers (collectors).  
5.4.3.  Vacuum systems  
5.4.3.1.  Specially designed or prepared large vacuum manifolds, vacuum 
headers, and vacuum pumps having a suction capacity of 5  m3/min. or more.  
5.4.3.2.  Specially designed vacuum pumps for use in an environment containing 
UF 6, made of or coated with material resistant to corrosion by UF 6, which for this item is 
defined as copper, copper alloys, stainless steel, alumin ium, aluminium alloys, aluminium 
oxide, nickel or its alloys containing at least 60  % nickel, and fluoropolymers. These may be 
designed as rotary or volume type. They may have fluorinated hydrocarbon polymer plugs 
and seals and may use special working flui ds. 
5.4.4.  Special shut -off and control valves  
Specially designed or prepared bellows -sealed valves, manual or automatic, shut -off or 
control, for installation in main and auxiliary systems of gas diffusion enrichment plants, 
made of or coated with material resis tant to corrosion by UF 6, which for this item is defined 
as copper, copper alloys, stainless steel, aluminium, aluminium alloys, aluminium oxide, 
nickel or its alloys containing at least 60  % nickel, and fluoropolymers.  
5.4.5.  UF 6 analysis mass spectrometers and ion sources  
Specially designed or prepared mass spectrometers capable of on -line sampling from a stream 
of gaseous UF 6, which have:  
5.4.5.1.  the ability to measure ions with an atomic mass of 320 or greater and a 
unit resolution better than 1:320;  
5.4.5.2.  ion sources made of nickel, nickel and copper alloys containing at least 
60 % nickel by weight, or nickel and chrome alloys, or coated with these materials;   - 12 - 
5.4.5.3.  electron bombardment ionisation sources; and  
5.4.5.4.  a collector system suitable for isotopic analysis.  
5.5. Specially designed o r prepared systems, equipment and components for use in 
aerodynamic enrichment plants  
Specially designed or prepared systems, equipment and components for use in aerodynamic 
enrichment plants are items that come into direct contact with UF 6 process gas or directly 
regulate flow inside the cascade. All surfaces that come into contact with the process gas are 
made of or protected by UF 6-resistant materials. These items include:  
5.5.1.  Separation nozzles  
Specially designed or prepared separation nozzles or assemblies  thereof. Separation nozzles 
consist of curved slit channels with a curve radius less than 1  mm. They are made of material 
resistant to corrosion by UF 6, which for this item is defined as copper, copper alloys, stainless 
steel, aluminium, aluminium alloys,  aluminium oxide, nickel or its alloys containing at least 
60 % nickel by weight, and fluoropolymers. Inside the nozzle there is a blade that splits the 
gas flowing through the nozzle into two fractions.  
5.5.2.  Vortex tubes  
Specially designed or prepared vortex t ubes or assemblies thereof. Vortex tubes are 
cylindrical or conical, made of or protected by material resistant to corrosion by UF 6, which 
for this item is defined as copper, copper alloys, stainless steel, aluminium, aluminium alloys, 
aluminium oxide, nic kel or its alloys containing at least 60  % nickel by weight, and 
fluoropolymers. The tubes have one or more tangential inlets and may have nozzles at one or 
both ends of the tube. Process gas enters the vortex tube tangentially at one end, or through 
swirl  vanes  or at numerous tangential positions along the periphery of the tube.  
5.5.3.  Compressors and gas blowers  
Specially designed or prepared compressors or gas blowers made of or protected by material 
resistant to corrosion by UF 6 and the carrier gas (hydrogen o r helium), which for this item is 
defined as copper, copper alloys, stainless steel, aluminium, aluminium alloys, aluminium 
oxide, nickel or its alloys containing at least 60  % nickel by weight, and fluoropolymers.  
5.5.4.  Rotary shaft seals  
Specially designed or prepared vacuum seals for sealing feed and exhaust flanges serving to 
seal 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 to  seal gas 
into the inner chamber of the compressor or gas blower which is filled with a UF 6/carrier gas 
mixture.  
5.5.5.  Heat exchangers for gas cooling  
Specially designed or prepared heat exchangers made of or protected by material resistant to 
corrosion by UF 6, which for this item is defined as copper, copper alloys, stainless steel, 
aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing at least 60  % 
nickel by weight, and fluoropolymers.  
5.5.6.  Separation element housings  
Specially designed or pr epared separation element housings made of or protected by material 
resistant to corrosion by UF 6, which for this item is defined as copper, copper alloys, stainless 
steel, aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing at le ast 
60 % nickel by weight, and fluoropolymers, housing vortex tubes or separation nozzles.  
5.5.7.  Feed systems and systems for removal of ‘products’ and ‘tails’  
Specially designed or prepared enrichment plant systems or equipment made of or coated with 
material r esistant to corrosion by UF 6, which for this item is defined as copper, copper alloys, 
stainless steel, aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing 
at least 60  % nickel by weight, and fluoropolymers, including:   - 13 - 
5.5.7.1.  Feed autocl aves, ovens  or systems used for passing UF 6 to the 
enrichment process.  
5.5.7.2.  Desublimers or cold traps used to eliminate UF 6 from the enrichment 
process for subsequent transport after heating.  
5.5.7.3.  Solidification or liquefaction stations used to remove UF 6 from the 
enrichment process by compression and transformation of UF 6 to a liquid or solid.  
5.5.7.4.  ‘Product’ and ‘tails’ stations used for trapping UF 6 into containers.  
5.5.8.  Header piping systems (collectors)  
Specially designed or prepared header piping systems (collectors) for UF 6 transport inside 
aerodynamic cascades, made of or coated with material resistant to corrosion by UF 6, which 
for this item is defined as copper, copper alloys, stainless steel, aluminium, aluminium alloys, 
aluminium oxide, nickel or its alloys containin g at least 60  % nickel by weight, and 
fluoropolymers. This piping network is normally designed as a double header (collector) 
system with each stage or group of stages connected to each of the headers (collectors).  
5.5.9.  Vacuum systems and pumps  
5.5.9.1.  Specially design ed or prepared vacuum systems consisting of vacuum 
manifolds, vacuum headers (collectors), and vacuum pumps  and designed for service in UF 6.-
bearing atmospheres.  
5.5.9.2.  Specially designed or prepared vacuum pumps for use in an 
environment containing UF 6, made of or protected by material resistant to corrosion by UF 6, 
which for this item is defined as copper, copper alloys, stainless steel, aluminium, aluminium 
alloys, aluminium oxide, nickel or its alloys containing at least 60  % nickel by weight, and 
fluoropolyme rs. These pumps may use fluorocarbon seals and special working fluids.  
5.5.10.  Special shut -off and control valves  
Specially designed or prepared bellows -sealed valves, manual or automatic, shut -off or 
control, made of or protected by material resistant to corrosi on by UF 6, which for this item is 
defined as copper, copper alloys, stainless steel, aluminium, aluminium alloys, aluminium 
oxide, nickel or its alloys containing at least 60  % nickel by weight, and fluoropolymers, with 
at least 40  mm diameter, which are i nstalled on main and auxiliary systems of aerodynamic 
enrichment plants.  
5.5.11.  UF 6 analysis mass spectrometers and ion sources  
Specially designed or prepared mass spectrometers capable of on -line sampling from a stream 
of gaseous UF 6 that have:  
5.5.11.1.  the ability to me asure ions with an atomic mass of 320 or greater and a 
unit resolution better than 1:320;  
5.5.11.2.  ion sources made of nickel, nickel and copper alloys containing at least 
60 % nickel by weight, or nickel and chrome alloys, or coated with these materials;  
5.5.11.3.  electron bombardment ionisation sources; and  
5.5.11.4.  a collector system suitable for isotopic analysis.  
5.5.12.  Systems for separation of UF 6 from carrier gas  
Specially designed or prepared process systems for separating UF 6 from carrier gas (hydrogen 
or helium). These systems are  designed to reduce the UF 6 content in the carrier gas to 1  ppm 
or less and may contain the following equipment:  
5.5.12.1.  Cryogenic heat exchangers or cryoseparators capable of temperatures of 
153 K (-120 °C) or less.  
5.5.12.2.  Cryogenic refrigeration units capable of temper atures of 153  K (-
120 °C) or less.  
5.5.12.3.  Separation nozzles or vortex tubes for the separation of UF 6 from the 
carrier gas.  
5.5.12.4.  UF 6 cryogenic separators capable of cryogenic separation of UF 6.  - 14 - 
5.6. Specially designed or prepared systems, equipment and components for use in 
enrichment plants, based on chemical or ion exchange  
5.6.1.  Liquid -liquid exchange columns (chemical exchange)  
Countercurrent liquid -liquid exchange columns having mechanical power input, specially 
designed or prepared for uranium enrichment using the chemical  exchange process. For 
corrosion resistance to concentrated HCl solutions, these columns and their internals are made 
of or protected by suitable plastic materials (such as fluorocarbon polymers) or glass. In the 
standard version, the filter reservoir is d esigned for a maximum of 30  seconds.  
5.6.2.  Liquid -liquid centrifugal extractors (chemical exchange)  
Specially designed or prepared liquid -liquid centrifugal extractors for uranium enrichment 
using the chemical exchange process. Such extractors use rotation to ac hieve dispersion of the 
organic and aqueous streams and then centrifugal force to separate the phases. For corrosion 
resistance to HCl, these columns and their internals are made of or protected by suitable 
plastic materials (such as fluorocarbon polymers)  or glass. In the standard version, the 
reservoir in centrifugal extractors is designed for a maximum of 30  seconds.  
5.6.3.  Uranium reduction systems and equipment (chemical exchange)  
5.6.3.1.  Specially designed or prepared electrochemical reduction cells to 
reduce uraniu m from one valence state to another for uranium enrichment using the chemical 
exchange process. Cell materials that come into contact with process solutions are corrosion 
resistant to concentrated HCl solutions. The cell cathodic compartment must be design ed to 
prevent re -oxidation of uranium to its higher valence states. To keep the uranium in the 
cathodic compartment, cells may have impervious diaphragm membranes constructed of 
special cation exchange material. The cathode consists of a suitable solid con ductor such as 
graphite.  
5.6.3.2.  Specially designed or prepared systems for taking the U+4 out of the 
organic stream at the product end of the cascade, adjusting the acid concentration  and feeding 
to the electrochemical reduction cells. Those parts of the system t hat come into contact with 
process streams are made of or protected by suitable materials (such as glass, fluorocarbon 
polymers, polyphenyl sul fate, polyether sulphone  and resin -impregnated graphite).  
5.6.4.  Feed solution preparation systems (chemical exchange)  
Specially designed or prepared systems for producing high -purity UCl 3 feed solutions for 
chemical exchange enrichment plants. These systems contain equipment for purification using 
solvents or cleaning using ion exchange through electrolytic reduction of U+6 or U+4 to U+3. 
These systems produce UCl 3 that contain just a few ppm metal impurities, especially chrome, 
iron, vanadium, molybdenum  and other bivalent or multivalent cations. Parts of the system 
that process highly pure U+3 are made of glass, fluorocar bon polymers, polyphenyl sul fate, 
polyether sulphone  or resin -impregnated graphite.  
5.6.5.  Uranium oxidation systems (chemical exchange)  
Specially 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. These systems may 
include the following equipment:  
5.6.5.1.  Equipment for mixing chlorine and oxygen with the aqueous effluent 
from the isotope separation equipment and extracting the resultant U+4 into the stripped 
organic st ream returning from the product end of the cascade.  
5.6.5.2.  Equipment that separates water from HCl so that they can be returned to 
the process at appropriate points.  
5.6.6.  Fast-reacting ion exchange resins/adsorbents (ion exchange)  
Fast-reacting ion  exchange resins or adsorbents specially designed or prepared for uranium 
enrichment using the ion exchange process, including porous macro -reticular resins, and/or 
pellicular structures in which the active chemical exchange groups are limited to a coating on  - 15 - 
the surface of a n inactive porous support structure or other composite structures of 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 HCl solutions as well a s 
physically strong enough so as not to degrade in the exchange columns. The resins/adsorbents 
are specially designed to achieve very fast uranium isotope exchange kinetics (exchange rate 
half-time of less than 10  seconds) and are capable of operating at t emperatures between 
373 K (100 °C) and 473  K (200 °C). 
5.6.7.  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, specially designed or prepared for u ranium 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 HCl solutions and are 
capable of operating at temperatures between 373  K (100 °C) and 473  K (200 °C) and 
pressures above 0.7  MPa.  
5.6.8.  Ion exchange reflux systems (ion exchange)  
5.6.8.1.  Specially designed or prepared chemical or electrochemical reduction 
systems for regeneration of chemical reducing agents used in ion exchange uranium 
enrichment cascades. During ion exchange enrichment, Ti+3 can for example be used as the 
reducing cation. In this case, the reduction system would reduce Ti+4 and thus generate Ti+3. 
5.6.8.2.  Specially designed or prepared chemical or electrochemical oxidation 
systems  for regeneration of chemical oxidising agents used in ion exchange uranium 
enrichment cascades. During this process, Fe+3 can, for example, be used as the reducing 
cation. In this case, the oxidation system would oxidise Fe+2 and thus generate Fe+3. 
5.7. Speci ally designed or prepared systems, equipment and components for use in 
laser -based enrichment plants  
Specially designed or prepared systems for the laser -based enrichment process include atomic 
vapour laser isotope separation where the process medium is at omic uranium vapour, and 
molecular vapour laser isotope separation, where the process medium is a uranium compound 
vapour, possibly mixed with other gas(es). The normal nomenclature for such processes 
includes: (first category) atomic vapour laser isotope separation, or (second category) 
molecular laser separation including chemical reaction by isotope selective laser activation. 
Current laser -based enrichment systems include: devices to feed uranium  metal vapour (for 
selective photo -ionisation) or devices to feed the vapour of a uranium compound (for photo -
dissociation or chemical activation), devices to collect enriched and depleted uranium metal 
as ‘product’ and ‘tails’ in the first category, and devices to collect dissociated or reacted 
compounds as ‘pro duct’ and unaffected material as ‘tails’ in the second category, process 
laser systems to selectively excite the 235U species, and feed preparation and product 
conversion equipment. The complexity of the spectroscopy of uranium atoms and compounds 
may requ ire incorporation of any of a number of available laser and laser optic technologies.  
Items specified in Item  5.7 that come into direct contact with gaseous or liquid uranium metal 
or with process gas consisting of UF 6 or a mixture of UF 6 with another gas have all surfaces 
that come into direct contact with uranium or UF 6, made of or protected by corrosion -resistant 
materials. For purposes of this item, materials resistant to corrosion by gaseous or liquid 
uranium metal or uranium alloys are, for example, g raphite coated with yttrium and tantalum. 
For this item materials resistant to corrosion by UF 6 are defined as copper, copper alloys, 
stainless steel, aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing 
at least 60  % nickel by wei ght, and fluoropolymers.   - 16 - 
5.7.1.  Uranium evaporation systems (atomic uranium vapour separation 
methods)  
Specially designed or prepared evaporation systems for laser enrichment of metal uranium. 
These systems may contain high -power electron beam guns with a deliver ed power on the 
target of at least 1  kW, which is sufficient for generating uranium metal vapours required for 
laser enrichment.  
5.7.2.  Systems and components for handling liquefied or gaseous uranium metal 
(atomic uranium vapour separation methods)  
Specially des igned or prepared systems or components used in handling molten uranium, 
molten uranium alloys  or uranium metal vapours for laser enrichment. Systems and 
components for handling liquid uranium may contain crucibles and equipment for cooling 
these crucibles . The crucibles and other parts of this system that come into contact with 
molten uranium or uranium alloys are made of or protected by materials of suitable heat -
resistant and corrosion -resistant materials. Suitable materials include graphite coated with 
yttrium oxide, graphite coated with oxides of other rare earth metals, or mixtures thereof.  
5.7.3.  Uranium metal ‘product’ and ‘tails’ header (collector) assemblies (atomic 
uranium vapour separation methods)  
Specially designed or prepared ‘product’ (enriched uran ium) and ‘tails’ (depleted uranium) 
header (collector) assemblies for uranium metal in liquid or solid form. These collector 
assemblies are made of or protected by materials resistant to the heat and corrosion of 
uranium metal vapour or molten uranium (for  example yttria -coated graphite or tantalum). 
This includes pipes, valves, fittings, grooves, bushings, heat exchangers  and collector plate 
electrodes for magnetic, electrostatic  or other separation methods.  
5.7.4.  Separation module housings (atomic uranium vapou r separation methods)  
Specially designed or prepared cylindrical or rectangular vessels for containing the uranium 
metal vapour source, the electron beam gun, and the ‘product’ (enriched uranium) and ‘tails’ 
(depleted uranium) headers (collectors). These h ousings have openings for electrical and 
water bushings, laser beam windows, vacuum pump connections  and instrumentation 
diagnostics and monitoring. They have provisions for opening and closure to allow 
refurbishment of internal components.  
5.7.5.  Ultrasonic expa nsion nozzles (molecular uranium vapour separation 
methods)  
Specially designed or prepared supersonic expansion nozzles for cooling mixtures of UF 6 and 
carrier gas to 150  K (-123 °C) or less that are resistant to corrosion by UF 6. For this item 
materials r esistant to corrosion by UF 6 are defined as copper, copper alloys, stainless steel, 
aluminium, aluminium alloys, aluminium oxide, nickel or its alloys containing at least 60  % 
nickel by weight, and fluoropolymers.  
5.7.6.  ‘Product’ and ‘tails’ collectors (molecula r uranium vapour separation 
methods)  
Specially designed or prepared components or equipment for collection of uranium ‘product’ 
or uranium ‘tails’ after laser irradiation. In one possible molecular laser separation, ‘product’ 
collectors are used to collect  enriched uranium pentafluoride (UF 5) in solid form. ’Product’ 
collectors may include a filter, impact, or cyclone type headers (collectors) or combinations 
thereof, and made of materials resistant to corrosion by UF 5 or UF 6. 
5.7.7.  Compressors for process gas an d UF 6 (molecular uranium vapour 
separation methods)  
Specially designed or prepared compressors for UF 6/carrier gas mixtures, designed for long -
term operation in a UF 6 environment. Components of these compressors that come into 
contact with process gas are made of or coated with material resistant to corrosion by UF 6, 
which for this item is defined as copper, copper alloys, stainless steel, aluminium, aluminium  - 17 - 
alloys, aluminium oxide, nickel or its alloys containing at least 60  % nickel by weight, and 
fluor opolymers.  
5.7.8.  Shaft seals (molecular uranium vapour separation methods)  
Specially 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 UF 6/carrier gas mixture.  
5.7.9.  Fluorination systems (molecular uranium vapour separation methods)  
Specially desig ned or prepared systems for fluorination of U 5 (in solid form) to U 6 (gas), 
which is subsequently collected in ‘product’ containers or immediately feeds additional 
enrichment units.  
5.7.10.  UF 6 analysis mass spectrometers and ion sources (molecular uranium 
vapour separation methods)  
Specially designed or prepared mass spectrometers capable of on -line sampling from a stream 
of gaseous UF 6 that have:  
5.7.10.1.  the ability to measure ions with an atomic mass of 320 or greater and a 
unit resolution better than 1:320;  
5.7.10.2.  ion sources  made of nickel, nickel and copper alloys containing at least 
60 % nickel by weight, or nickel and chrome alloys, or coated with these materials;  
5.7.10.3.  electron bombardment ionisation sources; and  
5.7.10.4.  a collector system suitable for isotopic analysis.  
5.7.11.  Feed systems a nd systems for removal of ‘products’ and ‘tails’ (molecular 
uranium vapour separation methods)  
Specially designed or prepared enrichment plant systems or equipment made of or protected 
by material resistant to corrosion by UF 6, which for this item is defin ed as copper, copper 
alloys, stainless steel, aluminium, aluminium alloys, aluminium oxide, nickel or its alloys 
containing at least 60  % nickel by weight, and fluoropolymers:  
5.7.11.1.  Feed autoclaves, ovens  or systems used for passing UF 6 to the 
enrichment process . 
5.7.11.2.  Desublimers or cold traps used to eliminate UF 6 from the enrichment 
process for subsequent transport after heating.  
5.7.11.3.  Solidification or liquefaction stations used to remove UF 6 from the 
enrichment process by compression and transformation of UF 6 to a liqui d or solid.  
5.7.11.4.  ‘Product’ and ‘tails’ stations used for trapping UF 6 into containers.  
5.7.12.  Systems for separation of UF 6 from process gas (molecular uranium 
vapour separation methods)  
Specially designed or prepared process systems for separating UF 6 from carrier ga s. The 
carrier gas may be nitrogen, argon  or other gas. These systems may include the following 
equipment:  
5.7.12.1.  Cryogenic heat exchangers or cryoseparators capable of temperatures of 
153 K (-120 °C) or less.  
5.7.12.2.  Cryogenic refrigeration units capable of temperatures  of 153  K (-
120 °C) or less.  
5.7.12.3.  UF 6 cryogenic separators capable of cryogenic separation of UF 6. 
5.7.13.  Laser systems  
Lasers or laser systems specially designed or prepared for the separation of uranium isotopes. 
A laser system usually contains optical and electroni c components for guiding beams and 
transmission to the isotope separation cell. Laser systems for atomic uranium vapour 
separation methods usually consist of two lasers: dye -based tunable lasers augmented by a 
different laser type; for example, a copper va pour laser or a solid -state laser. Laser systems for  - 18 - 
molecular uranium vapour separation methods usually consist of CO 2 lasers or excimer lasers 
and a multi -pass optical cell. Lasers or laser systems utilising both methods require 
wavelength (frequency) st abilisation for long -term operation.  
5.8. Specially designed or prepared systems, equipment  and components for use in 
plasma separation enrichment plants  
The main technological systems of this process include the uranium plasma generation 
system, the separator module with superconducting magnet, and metal removal systems for 
the collection of ‘product’ and ‘tails’.  
5.8.1.  Microwave power sources and antennae  
Specially designed or prepared microwave power sources and antennae for ion generation or 
acceleration that have  frequencies greater than 30  GHz and capable of handling more than 
50 kW mean power.  
5.8.2.  Ion excitation coils  
Specially designed or prepared radio -frequency ion excitation coils for frequencies greater 
than 100  kHz and capable of handling more than 40  kW mean power.  
5.8.3.  Uranium plasma generation systems  
Specially designed or prepared systems for creation of uranium plasma for use in plasma 
separation enrichment plants.  
5.8.4.  Uranium metal ‘product’ and ‘tails’ collector assemblies  
Specially designed or prepared ‘product’  and ‘tails’ collector assemblies for uranium metal in 
solid form. These collector assemblies are made of or coated with materials resistant to the 
heat and corrosion of uranium metal vapour, such as yttria -coated graphite or tantalum.  
5.8.5.  Separator module hou sings  
Cylindrical vessels specially 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. These housings have openings for electric al bushings, diffusion pump 
connections  and diagnostics and monitoring system sensors. They have provisions for 
opening and closure to allow for replacement of internal components and are constructed of a 
suitable non -magnetic material such as stainless st eel. 
5.9. Specially designed or prepared systems, equipment  and components for use in 
electromagnetic enrichment plants  
5.9.1.  Electromagnetic isotope separators  
Electromagnetic isotope separators specially designed or prepared for the separation of 
uranium isotopes, and equipment and components intended for this purpose:  
5.9.1.1.  Ion sources  
Specially designed or prepared single or multiple uranium ion sources consisting of a vapour 
source, ioniser  and beam accelerator, constructed of materials such as graphite, stainless stee l, 
or copper, and capable of providing a total ion beam current of 50  mA or greater.  
5.9.1.2.  Ion headers (collectors)  
Header (collector) plates consisting of two or more slits and pockets specially designed or 
prepared for collection of enriched and depleted urani um ion beams and made of materials 
such as graphite or stainless steel.  
5.9.1.3.  Vacuum housings  
Specially designed or prepared vacuum housings for electromagnetic separators, made of non -
magnetic materials such as stainless steel and designed for operation at pres sures of 0.1  Pa or 
lower. Housings are specially designed to contain ion sources, collection plates  and water -
cooled liners, have provisions for diffusion pump connection, and may have openings for 
removal and re -installation of internal components.   - 19 - 
5.9.1.4.  Magnet  pole pieces  
Specially 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.  
5.9.2.  High -voltage power supplies  
Specially designed or prepared high -voltage power supplies for ion sources, having the 
following characteristics:  
5.9.2.1.  capable of continuous operation;  
5.9.2.2.  input voltage of 20  kV or greater;  
5.9.2.3.  output current of 1  A or greater;  
5.9.2.4.  voltage regulatio n better than 0.01  % over 8 hours.  
5.9.3.  Electromagnet power supplies  
Specially designed or prepared high -power, direct current magnet power supplies having the 
following characteristics:  
5.9.3.1.  the ability to continuously deliver output current of 500  A or greater at 
a voltage of 100  V or more; and  
5.9.3.2.  current or voltage regulation better than 0.01  % over 8 hours.  
 
6. Plants for the production or modification of concentration of heavy water, deuterium  
and its compounds and devices specially designed or prepared for this purpo se 
Equipment which is especially designed or prepared for the production of heavy water 
utilising either the water -hydrogen sul fide exchange process or the ammonia -hydrogen 
exchange process include parts of equipment that are not specially designed or prep ared for 
the production of heavy water, but are installed in systems that are specially designed or 
prepared for this production. Items corresponding to the term ‘equipment specially designed 
or prepared for the production of heavy water’ include:  
6.1. Water -hydrogen sul fide exchange columns  
Ammonia -hydrogen exchange columns with diameters of at least 1.5  m capable of operating 
at pressures equal to or greater than 2  MPa, specially designed or prepared for heavy water 
production utilising the ammonia -hydrogen ex change process.  
6.2. Blowers and compressors  
Single stage, low head (i.e. 0.2  MPa) centrifugal blowers or compressors specially designed or 
prepared for circulation of gas containing more than 70  % H2S used in heavy water 
production utilising the water -hydrogen  sulfide exchange process. These blowers or 
compressors have a minimum output of 56  m3/s while operating at pressures greater than or 
equal to 1.8  MPa and have seals designed for wet H 2S service.  
6.3. Ammonia -hydrogen exchange columns  
Exchange columns with a mi nimum height of 35  m and diameter of 1.5 -2.5 m capable of 
operating at pressures greater than 15  MPa and specially designed or prepared for heavy water 
production utilising the ammonia -hydrogen exchange process. These columns 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.  
6.4. Column internals and stage pumps  
Column internals and stage pumps specially designed or prepared for columns for heavy 
water produc tion utilising the ammonia -hydrogen exchange process. Column internals include 
specially designed stage contactors that ensure the best possible gas/liquid contact. Stage 
pumps are specially designed submersible pumps for circulation of liquid ammonia with in a 
contacting stage and for ammonia transport to the column stages.   - 20 - 
6.5. Ammonia crackers  
Ammonia crackers with operating pressures greater than or equal to 3  MPa specially designed 
or prepared for heavy water production utilising the ammonia -hydrogen exchang e process.  
6.6. Infrared absorption analysers  
Infrared absorption analysers capable of on -line hydrogen/deuterium ratio analysis where 
deuterium concentrations are equal to or greater than 90  %. 
6.7. Catalytic burners  
Catalytic burners for the conversion of enriched  deuterium gas into heavy water specially 
designed or prepared for heavy water production utilising the ammonia -hydrogen exchange 
process.  
6.8. Complete heavy water upgrade systems or columns intended for this purpose  
Complete heavy water upgrade systems or col umns specially designed or prepared for 
achieving deuterium concentration required for use in a nuclear reactor. These systems, which 
usually employ water distillation to separate heavy water from light water, are specially 
designed or prepared distillatio n units that produce reactor -grade heavy water (typically 
99.75  % deuterium oxide) from heavy water feedstock of lesser concentration.  
6.9. Ammonia synthesis converters or synthesis units  
Ammonia synthesis converters or synthesis units specially designed or pre pared for heavy 
water production utilising the ammonia -hydrogen exchange process. These converters or units 
receive the synthesis gas (nitrogen and hydrogen) from an ammonia/hydrogen high -pressure 
exchange column and the synthesised ammonia is returned to said column.  
 
7. Plants for the conversion of uranium and plutonium for use in the manufacture of 
fuel elements and the separation of uranium isotopes and equipment specially 
designed or prepared for this purpose  
7.1. Plants for the conversion of uranium and equip ment specially designed or 
prepared for this purpose  
Plants for the conversion of uranium, in which one or more uranium transformations can be 
performed from one of its chemical forms to another, defined as the conversion of uranium 
ore concentrates to UO 3, conversion of UO 3 to UO 2, conversion of uranium oxides to UF 4, 
UF 6 or UCl 4 conversion of UF 4 to UF 6, conversion of UF 6 to UF 4, conversion of UF 4 to 
uranium metal, and conversion of uranium fluorides to UO 2. 
In all of the uranium conversion processes, ite ms of equipment which individually are not 
specially designed or prepared for uranium conversion can be assembled into systems which 
are specially designed or prepared for use in uranium conversion.  
7.1.1.  Specially designed or prepared systems for the conversion  of uranium ore 
concentrates to UO 3 
Systems for conversion of uranium ore concentrates to UO 3 by dissolving ore in HNO 3 and 
extraction of pure UO 2(NO 3)2 with the use of C 12H27O4P as solvents. UO 2(NO 3)2 is then 
converted to UO 3 either using concentration an d denitrification or neutralisation with 
ammonia gas until the creation of (NH 4)2U2O7 with subsequent filtering, drying  and baking.  
7.1.2.  Specially designed or prepared systems for the conversion of UO 3 to UF 6 
Systems for the conversion of UO 3 to UF 6 through dir ect fluorination using fluorine gas or 
ClF 3 as sources of fluorine.  
7.1.3.  Specially designed or prepared systems for the conversion of UO 3 to UO 2 
Systems for conversion of UO 3 to UO 2 through the reduction of UO 3 by cracked ammonia gas 
or hydrogen.  
7.1.4.  Specially desi gned or prepared systems for the conversion of UO 2 to UF 4 
Systems for conversion of UO 2 to UF 4 based on a reaction of UO 2 with gaseous HF at 300 -
500 °C.  - 21 - 
7.1.5.  Specially designed or prepared systems for the conversion of UF 4 to UF 6 
Systems for conversion of UF 4 to UF 6, through an exothermic reaction with fluorine in 
column reactors, where UF 6 is condensed in hot effluent gases while passing through a cold 
trap cooled to -10 °C. This process requires a source of fluorine gas.  
7.1.6.  Specially designed or prepared systems for the conversion of UF 4 to 
uranium metal  
Systems for conversion of UF 4 to uranium metal 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). 
7.1.7.  Specially designed or prepared systems for the conversion of UF 6 to UO 2 
Systems of conversion of UF 6 to UO 2 through reduction of UF 6 and hydrolysis to UO 2 with 
the use of hydrogen and steam, or hydrolysis of UF 6 by dissolution in water and precipitation 
of (N H4)2U2O7 by adding ammonia, where (NH 4)2U2O7 is then reduced to  UO 2 using 
hydrogen at 820  °C, or through reaction of gaseous UF 6, CO 2 and ammonia gas in water, 
precipitating UO 2(CO 3)3(NH 4)4. When UO 2(CO 3)3(NH 4)4 reacts with steam and hydrogen at 
500-600 °C, the result is UO 2. 
7.1.8.  Specially designed or prepared systems for the conversion of UF 6 to UF 4 
Systems for conversion of UF 6 to UF 4 through reduction by hydrogen.  
7.1.9.  Specially designed or prepared systems for the conversion of UO 2 to UCl 4 
Systems for the conver sion of UO 2 to UCl 4 through reaction of UO 2 with CCl 4 at 
approximately 400  °C, reaction of UO 2 at approximately 700  °C in the presence of soot 
(carbon black) (CAS  1333 -86-4), CO, and chlorine, producing UCl 4. 
7.2. Plants for the conversion of plutonium and equi pment specially designed or 
prepared for this purpose  
Plants and systems for the conversion of plutonium, in which Pu(NO 3)3 is converted to PuO 2, 
PuO 2 is converted to PuF 4, and PuF 4 is converted to plutonium metal.  
In all of the plutonium conversion proces ses, items of equipment which individually are not 
specially designed or prepared for plutonium conversion can be assembled into systems which 
are specially designed or prepared for use in plutonium conversion.  
7.2.1.  Specially designed or prepared systems for th e conversion of plutonium 
nitrate to oxide  
Systems for the conversion of plutonium nitrate to oxide using precipitation, separation  and 
calcination processes. The process systems are particularly adapted so as to avoid criticality 
and radiation effects and  to minimise toxicity hazards.  
7.2.2.  Specially designed or prepared systems for plutonium metal production  
Systems for the production of plutonium metal through fluorination of plutonium oxide with 
highly corrosive hydrogen fluoride in order to produce plutonium  fluoride, which is reduced 
through the use of highly pure calcium metal to obtain plutonium metal, or fluorination with 
plutonium oxalate with subsequent reduction to metal, or fluorination of plutonium peroxide 
with subsequent reduction to metal. The pro cess systems are particularly adapted so as to 
avoid criticality and radiation effects and to minimise toxicity hazards.  
 
8. Packaging for irradiated nuclear fuel and hot cells  
8.1. Packaging for irradiated nuclear fuel  
Packaging for the transportation and/or stor age of irradiated nuclear fuel, which provides 
chemical, thermal and radiation protection, and removal of decay heat during handling, 
transportation and storage.   - 22 - 
8.2. Hot cells  
Hot cells or interconnected hot cells with a total volume of at least 6  m3 and shiel ding 
corresponding to the equivalent of 0.5  m or more concrete, with a density of 3.2  g/cm3 or 
higher, with facilities for remote control.  
 
9. Technology  
Technology directly related to any item specified in points  1 to 8, except for information in 
the public domain or basic scientific research.  
 
10. Software  
Software directly related to any item specified in points  1 to 8, except for software related to 
information in the public domain or basic scientific research.  
 
Notes for the annex : 
Microprogram me – a sequence  of elementary instructions, maintained in a special storage, the execution of 
which is initiated by the introduction of its reference instruction into an instruction register.  
Other element – an element other than hydrogen, uranium  or plutonium.  
Use – is operation, installation (including on -site installation), and maintenance, including checking, repair, 
overhaul  or refurbishing.  
Program me – a sequence of instructions to perform a process that is in a form or transferable to a form that can 
be processed b y a computer.  
Software - a file containing one or more program mes or microprogram mes on any physical medium.  
Technical information – a drawing, plan, diagram, model, formula, technical design or specification, manual or 
instructions in written form, or dat a recorded on media.  
Technical assistance – instructions, skills, training, work experience, consulting service; technical assistance may 
also include technical information.  
Manufacturing – a production phase, for example, construction, manufacturing engin eering, manufacture, 
integration, installation (attachment), checking, testing, quality assurance.  
Development - a pre -production phase, for example, design, research in the area of design, design analysis, 
design conceptualisation, prototype assembly and testing, pilot production schemas, construction information, 
the process of transforming construction information into a product, configuration design, integration design.  
Technology – specific information needed for development, production  or use of any o f the items in this annex; 
such information may take the form of technical information or technical assistance.  
Public domain – technology or software that has been made available without restrictions on its further use; 
copyright -related restrictions do n ot disqualify technologies or software from the public domain.  
Basic scientific research – experimental or theoretical work undertaken principally to acquire new knowledge of 
the fundamental principles of phenomena and observable facts, not primarily direc ted towards a specific 
practical aim or objective.  
  - 23 - 
Annex  2 to Decree No  .../…  
 
Declaration  
 
by the end -user of a selected nuclear item  
 
 
Information on an end -user that is a corporate subject  
Name:  
Registered offices:  
Identification number:  
Information  on an end -user that is a natural person  
Name(s) and surname(s):  
Business address:  
Date of birth:   - 24 - 
Specification of the nuclear item that the declaration concerns  
 
Use and purpose of the nuclear item that the declaration concerns  
 
 
 
I declare that  
a) I shall not use the selected nuclear item or part thereof for any purposes contrary to the 
Treaty on the Non -Proliferation of Nuclear Weapons or to help achieve any military 
objectives;  
b) I shall make it possible to apply guarantees and control by the State Offi ce for Nuclear 
Safety (SONS), the European Community for Atomic Energy, and the International 
Atomic Energy Agency;  
c) I shall ensure physical protection in accordance with the Atomic Act;  
d) I shall not export a selected nuclear item or part thereof without the authorisation of the 
State Office for Nuclear Safety; and  
e) I shall notify the State Office for Nuclear Safety of transfer of a selected nuclear item or 
part thereof.  
 
 
 
 
 
_______________ _______________________  
Date and signature