Item No.

Name <*>

Code of the CN FEA EEU <*>

Section 1. Nuclear materials

1.1.

Initial material

1.1.1.

Uranium with content of isotopes in that relation in what they are in natural uranium, in the form of metal, alloy, chemical compound or concentrate

2844 10

1.1.2.

The uranium which is grown poor by isotope 235 in the form of metal, alloy, chemical compound or concentrate

2844 30 110 0;

2844 30 190 0

1.1.3.

Thorium in the form of metal, alloy, chemical compound or concentrate

2844 30 510 0;

2844 30 610 0;

2844 30 690 0

1.2.

The special splitting material

1.2.1.

Plutonium-239

2844 20 990 0

1.2.2.

Uranium-233

2844 43 000 0

1.2.3.

The uranium enriched with isotope 235 or 233

2844 20 350 0;

2844 43 000 0

Determination

The term "the uranium enriched with isotope 235 or 233", means the uranium containing isotope 235 or 233, or that and another together in such quantity that the relation of the amount of these isotopes to isotope 238 was more relation of isotope 235 to isotope 238 in natural uranium

1.2.4.

Any material containing one or several substances specified in Items 1.2.1 - 1.2.3 in the form of metal, alloy, chemical compound, concentrate, the fresh or fulfilled reactor fuel

2844 20;

2844 20 350 0;

2844 20 990 0;

2844 43 000 0;

2844 50 000 0;

8401 30 000 0

1.2.5.

The technologies connected with all materials included in Section 1 of this list

1.2.6.

The software connected with all materials included in Section 1 of this list

Note. Export control of plutonium with isotope concentration of plutonium-238 over 80 percent is exercised according to the list of the equipment and the materials of dual purpose and appropriate technologies applied in the nuclear purposes concerning which export control is exercised.

1.3.

Nuclides

1.3.1.

Neptuny-237, and also any material or the device containing it

2844 43 000 0

1.3.2.

Ameritsy-241, and also any material or the device containing it

2844 43 000 0

1.3.3.

Ameritsy-243, and also any material or the device containing it

2844 43 000 0

1.3.4.

Kaliforny-252, and also any material or the device containing it

2844 43 000 0

Note. Nuclides, materials and devices containing them specified in Items 1.3.1 - 1.3.4, with the activity which is not falling under action of Safety rules in case of transportation of radioactive materials are not subject to export control (NP-053-16)

Section 2. Equipment and non-nuclear materials

2.1.

Nuclear reactors and specially developed or prepared equipments and components for them

Introduction note. Different nuclear reactors can be classified depending on the used decelerator (for example, graphite, heavy water, regular water, and also lack of the decelerator), energies of range of neutrons in it (for example, thermal, bystry), the used heat carrier type (for example, water, liquid metals, fused salts, gases), their appointment or type (for example, power reactors, research reactors, test reactors). It is supposed that all specified types of nuclear reactors are subject of regulation of this Item and all its subitems where it is applicable. On Item 2.1 thermonuclear reactors are not subject to export control.

2.1.1.

Complete nuclear reactors.

The nuclear reactors capable to work in the mode of controlled self-sustaining chain reaction of division

8401 10 000 0

Explanatory note. The nuclear reactor generally includes the nodes which are in the reactor case or directly given it, the equipment which controls power level in active zone, and their parts which usually contain the heat carrier of the first contour of the reactor come to it into direct contact or regulate it.

2.1.2.

Cases of nuclear reactors.

Specially developed or prepared metal cases or the main parts of factory production for placement in them active zone of nuclear reactors as they are determined in Item 2.1. 1, and internal parts of reactors as they are determined in Item 2.1.8

8401 40 000 0

Explanatory note. Item 2.1.2 covers the cases of nuclear reactors which are turning on the case of the reactor and calenders irrespective of nominal rate of pressure. The cover of the case of the reactor is covered by Item 2.1.2 as the main part of the case of the reactor of factory production.

2.1.3.

Machines for loading and unloading of fuel of nuclear reactors.

Specially developed or prepared manipulyatorny equipment for loading or extraction of fuel from nuclear reactors as they are determined in Item 2.1.1

8426 19 000 0;

8426 99 000 0

Explanatory note. The machines determined in Item 2.1. 3, are used when the reactor is under loading, or have the technical capabilities for exact positioning or orientation allowing to carry out on the stopped reactor complex works on fuel overload during which direct observation or direct access to fuel are usually impossible.

2.1.4.

Managing cores of nuclear reactors and equipment.

Specially developed or prepared cores, supporting or suspended frameworks for them, the drives or the directing pipes for cores used for process control of division in nuclear reactors as they are determined in Item 2.1.1

8401 40 000 0

2.1.5.

Pipes of high pressure for nuclear reactors.

Specially developed or prepared pipes for placement in them fuel elements and the heat carrier of the first contour in nuclear reactors as they are determined in Item 2.1.1

7304;

7507 12 000 0;

7608 20;

8109 91 000 0;

8109 99 000 0;

8401 40 000 0

Explanatory note. The pipes of high pressure specified in Item 2.1.5 are part of canals for fuel and are intended for work with the high pressures sometimes exceeding 5 MPas.

2.1.6.

Covers of nuclear fuel.

Specially developed or prepared pipes from metal zirconium or zirconium alloys (or assemblies of pipes) for use as fuel covers in nuclear reactors as they are determined in Item 2.1. 1, in number of 10 kg and more

8109 91 000 0;

8109 99 000 0

Explanatory note. Pipes from zirconium or alloys of zirconium, held for use in nuclear reactors as fuel covers, consist of zirconium, and in them the relation on hafnium weight to zirconium is less than 1:500. Item 2.1 is applied to zirconium pipes of high pressure. 5, Item 2.1.8 is applied to pipes of calender.

2.1.7.

Pumps or circulators of the first contour of the heat carrier.

Specially developed or prepared pumps or circulators for maintenance of circulation of the heat carrier of the first contour of nuclear reactors as they are determined in Item 2.1.1

8413 81 000 0

Explanatory note. Specially developed or prepared pumps or circulators turn on pumps for the water-cooled reactors, circulators for the gas-cooled reactors, and also electromagnetic and mechanical pumps for reactors with the zhidkometallichesky heat carrier. This equipment can turn on pumps with complex systems of consolidations or systems of repeated consolidations for prevention of leakage of the heat carrier of the first contour, hermetic pumps and pumps with systems of inertial weight. This determination concerns the pumps certified for the first class of components according to the subsection NB of group I of the Section III of the Code of the American society of mechanical engineers (ASME) or other equivalent standard.

2.1.8.

Internal parts of nuclear reactors.

Specially developed or prepared internal parts for use in nuclear reactors as they are determined in Item 2.1. 1, the supporting columns of active zone which are including, for example, channels for fuel, calender pipes, thermal screens, partitions, pipe lattices of active zone and plate of the diffuser

8401 40 000 0

Explanatory note. Internal parts of nuclear reactors are the main structural elements in cases of reactors and have one or several appointments, such as support of active zone, deduction of assemblies of fuel, direction of flow of the heat carrier of the first contour, ensuring radiation protection of the case of the reactor and control of the equipment in active zone.

2.1.9.

Heat exchangers

2.1.9.1.

Specially developed or prepared steam generators for use in the first or intermediate contour of chilling of nuclear reactors as they are determined in Item 2.1.1

8402 19 900

2.1.9.2.

Specially developed or prepared other heat exchangers for use in the first contour of chilling of nuclear reactors as they are determined in Item 2.1.1

8404 20 000 0;

8419 50 000 0;

Explanatory note. Specially developed or prepared steam generators for transfer of heat generated in the reactor to feedwater for generation of vapor. At bystry reactors in which there is also intermediate contour the steam generator is in intermediate contour. In the gas-cooled reactor the steam generator can be used for transfer of heat to the secondary gas contour setting the gas turbine in motion. Item 2.1.9 does not cover heat exchangers for the supporting systems of the reactor, that is systems of emergency chilling or systems of withdrawal of residual heat release.