WHEREAS .......... (hereinafter referred to as "..........") is a party to (an)

Agreement(s) between .......... and the International Atomic Energy Agency

(hereinafter referred to as the "Agency") for the application of safeguards [full title

of the Agreement(s) to be inserted] (hereinafter referred to as the "Safeguards

Agreement(s)"), which entered into force on ...........;

AWARE OF the desire of the international community to further enhance

nuclear non-proliferation by strengthening the effectiveness and improving the

efficiency of the Agency's safeguards system

RECALLING that the Agency must take into account in the

implementation of safeguards the need to:  avoid hampering the economic and

technological development of .......... or international  co-operation in the field of

peaceful nuclear activities;  respect health, safety, physical protection and other

security provisions in force and the rights of individuals;  and take every precaution

to protect commercial, technological and industrial secrets as well as other

confidential information coming to its knowledge;

WHEREAS the frequency and intensity of activities described in this

Protocol shall be kept to the minimum consistent with the objective of

strengthening the effectiveness and improving the efficiency of Agency safeguards;

NOW THEREFORE .......... and the Agency have agreed as follows

MAP Article 1: 

RELATIONSHIP BETWEEN THE PROTOCOL AND THE SAFEGUARDS AGREEMENT

The provisions of the Safeguards Agreement shall apply to this Protocol to the extent that they are relevant to and compatible with the provisions of this Protocol.  In case of conflict between the provisions of the Safeguards Agreement and those of this Protocol, the provisions of this Protocol shall apply.

MAP Article 2 (a)

PROVISION OF INFORMATION

. .......... shall provide the Agency with a declaration containing:

MAP Article 2 (a) (i)

PROVISION OF INFORMATION

 A general description of and information specifying the location of nuclear fuel cycle-related research and development activities not involving  nuclear material carried out anywhere that are funded, specifically authorized or controlled by, or carried out on behalf of, .......... 

MAP Article 2 a(ii)

PROVISION OF INFORMATION

 Information identified by the Agency on the basis of expected gains in effectiveness or efficiency, and agreed to by .........., on operational activities of safeguards relevance at  facilities and at locations outside facilities where nuclear material is customarily used.

MAP Article 2 (a) (iii)

PROVISION OF INFORMATION

 A general description of each building on each site, including its use and, if not apparent from that description, its contents.   The description shall include a map of the site.

PROVISION OF INFORMATION

 A description of the scale of operations for each location engaged in  the activities specified in Annex I to this Protocol.

MAP Article 2 (a) (v)

PROVISION OF INFORMATION

Information specifying the location, operational status and the estimated annual production capacity of uranium mines and concentration plants and thorium concentration plants, and the current annual production of such mines and concentration plants for .......... as a whole.  .......... shall provide, upon request by the

Agency, the current annual production of an individual mine or concentration plant. The provision of this information does not require detailed nuclear material accountancy.

MAP Article 2 (a) (vi)

PROVISION OF INFORMATION

 Information regarding source material which has not reached the composition and purity suitable for fuel fabrication or for being isotopically enriched, as follows:

MAP Article 2 (a)(vi)(a)

PROVISION OF INFORMATION

The quantities, the chemical composition, the use or

intended use of such material, whether in nuclear or

non-nuclear use, for each location in ......... at which the material is present in quantities exceeding ten metric tons of uranium and/or twenty metric tons of thorium, and for other locations with quantities of more than one metric ton, the aggregate for .......... as a whole if the aggregate exceeds ten metric tons of uranium or twenty metric tons of thorium.  The provision of this information does not require detailed  nuclear material accountancy.

MAP Article 2 (a)(vi)(b)

PROVISION OF INFORMATION

(Text, Parts 1 & 2)

  The quantities, the chemical composition and the destination of each export out of .........., of such material for specifically non-nuclear purposes in quantities

exceeding:

(1) Ten metric tons of uranium, or for successive exports of uranium from ........... to the same State, each of less than ten metric tons, but exceeding a total of ten metric tons for the year;

(2) Twenty metric tons of thorium, or for successive exports of thorium from .......... to the same State, each of less than twenty metric tons, but exceeding a total of twenty metric tons for the year;

MAP Article 2 (a)(vi)(c)

PROVISION OF INFORMATION

(Preceeding Text, Parts 1 & 2, and concluding text)

 The quantities, chemical composition, current location and use or intended use of each import into ..........  of such material for specifically non-nuclear purposes in

quantities exceeding:

(1) Ten metric tons of uranium, or for successive imports of uranium into .......... each of less than ten metric tons, but exceeding a total of ten metric tons for the year;

(2) Twenty metric tons of thorium, or for successive imports of thorium into .......... each of less than twenty metric tons, but exceeding a total of twenty metric tons for the year;

it being understood that  there is no requirement to provide information on such material intended for a non-nuclear use once it is in its non-nuclear end-use form.

MAP Article 2 (a)(vii)(a)

PROVISION OF INFORMATION

(Text & Footnote)

Information regarding the quantities, uses and locations

of  nuclear material exempted from safeguards pursuant

to [paragraph 37 of INFCIRC/153] 2*

Footnote: The reference to the corresponding provision of the relevant Safeguards Agreement should be inserted where bracketed references to INFCIRC/153 are made

MAP Article 2 (a)(vii)(b)

PROVISION OF INFORMATION

 Information regarding the quantities (which may be in

the form of estimates) and uses at each location, of

nuclear material exempted from safeguards pursuant to

[paragraph 36(b) of INFCIRC/153] but not yet in a

non-nuclear end-use form, in quantities exceeding those

set out in [paragraph 37 of INFCIRC/153]The provision of this information does not require detailed nuclear material accountancy.

MAP Article 2 (a) (viii)

PROVISION OF INFORMATION

 Information regarding the location or further processing of intermediate or high-level waste containing plutonium,  high enriched uranium or uranium-233 on which safeguards have been terminated pursuant to [paragraph 11 of INFCIRC/153] For the   purpose of this paragraph, "further processing" does not include repackaging of the waste or its further conditioning not involving the separation of elements, for storage or disposal.

MAP Article 2 (a)(ix)

PROVISION OF INFORMATION

(Text and parts a & b)

 The following information regarding specified equipment and non-nuclear material listed in Annex II:

(a) For each export out of .......... of such equipment and material:  the identity, quantity, location of intended us in the receiving State and date or, as appropriate,expected date, of export;

(b) Upon specific request by the Agency, confirmation by ..........., as importing State, of information provided to the Agency by another State concerning the export of

such equipment and material to …………….. .”

MAP Article 2 (a)(x)

PROVISION OF INFORMATION

General plans for the succeeding ten-year period relevant to the development of the nuclear fuel cycle (including planned nuclear fuel cycle-related research and development activities) when approved by the appropriate authorities in ..........  .

MAP Article 2 (b) 

PROVISION OF INFORMATION

 .......... shall make every reasonable effort to provide the Agency with the following  information:

MAP Article 2 (b)(i)

PROVISION OF INFORMATION

 A general description of and information specifying the location of nuclear fuel cycle-related research and development activities not involving  nuclear material which are specifically related to enrichment, reprocessing of nuclear fuel or the processing of

intermediate or high-level waste containing plutonium,  high enriched uranium or uranium-233 that are carried out anywhere in .......... but which are not funded, specifically authorized or controlled by, or carried out on behalf of, .......... .  For the purpose of this paragraph, "processing" of intermediate or highlevel waste does not include repackaging of the waste or its conditioning not involving the separation of elements, for storage or disposal.

MAP Article 2 (b)(ii)

PROVISION OF INFORMATION

A general description of activities and the identity of the person or entity carrying out such activities, at locations identified by the Agency outside a  site  which the Agency considers might be functionally related to the  activities of that site.  The provision of this information is subject to a specific request by the Agency.  It shall be provided in consultation with the Agency and in a timely fashion.

MAP Article 2 (c)

PROVISION OF INFORMATION

 Upon request by the Agency, .......... shall provide amplifications or clarifications of any information it has provided under this Article, in so far as relevant for the purpose of safeguards.

MAP Article 3 (a)

PROVISION OF INFORMATION

 .......... shall provide to the Agency the information identified in Article  2.a.(i), (iii), (iv), (v), (vi)(a), (vii) and (x) and Article 2.b.(i) within 180 days of the entry into force of this Protocol.

MAP Article 3 (b)

PROVISION OF INFORMATION

 .......... shall provide to the Agency, by 15 May of each year, updates of the information referred to in paragraph a. above for the period covering the previous calendar year. If there has been no change to the information

previously provided, .......... shall so indicate.

MAP Article 3 (c)

PROVISION OF INFORMATION

 .......... shall provide to the Agency, by 15 May of each year, the information identified in Article 2.a.(vi)(b) and (c) for the period covering the previous calendar year.

MAP Article 3 (d)

PROVISION OF INFORMATION

 .......... shall provide to the Agency on a quarterly basis the information identified in Article 2.a.(ix)(a).  This information shall be provided within sixty days of the end of each quarter.

MAP Article 3 (e)

PROVISION OF INFORMATION

 .......... shall provide to the Agency the information identified in Article 2.a.(viii) 180 days before further processing is carried out and, by 15 May of each year, information on changes in location for the period covering

the previous calendar year.

MAP Article 3 (f)

PROVISION OF INFORMATION

 .......... and the Agency shall agree on the timing and frequency of the provision of the information identified in Article 2.a.(ii)

MAP Article 3(g)

PROVISION OF INFORMATION

 .......... shall provide to the Agency the information in Article 2.a.(ix)(b) within sixty days of the Agency's request.

MAP Article 4

COMPLIMENTARY ACCESS

The following shall apply in connection with the implementation of complementary access under Article 5 of this Protocol:

MAP Article 4 (a)

COMPLIMENTARY ACCESS

The Agency shall  not mechanistically or systematically seek to verify the information referred to in Article 2;  however, the Agency shall have access to:

MAP Article 4 (a)(i)

COMPLIMENTARY ACCESS

 Any location referred to in Article 5.a.(i) or (ii) on a selective basis in order to assure the absence of undeclared  nuclear material and activities.

MAP Article 4(a)(ii)

COMPLIMENTARY ACCESS

 Any location referred to in Article 5.b. or c. to resolve  a question relating to the correctness and completeness of the information provided pursuant to Article 2 or to resolve an inconsistency relating to that information.

MAP Article 4(a)(iii)

COMPLIMENTARY ACCESS

 Any  location referred to in Article 5.a.(iii) to the extent necessary for the Agency to confirm, for safeguards purposes, ..........'s declaration of the decommissioned status of a facility or of a location outside facilities where  nuclear material was customarily used.

MAP Article 4 (b) 

COMPLIMENTARY ACCESS

(parts i & ii)

 (i) Except as provided in paragraph (ii) below, the Agency shall give ..........advance notice of access of at least 24 hours; 

(ii) For access to any place on a site that is sought in conjunction with design information verification visits or ad hoc or routine inspections on that site, the period of advance notice shall, if the Agency so requests, be at least two hours but, in exceptional circumstances, it may be less than two hours.

MAP Article 4 (c)

COMPLIMENTARY ACCESS

 Advance notice shall be in writing and shall specify the reasons for access and the activities to be carried out during such access.

MAP Article 4 (d) 

COMPLIMENTARY ACCESS

 In the case of a question or inconsistency, the Agency shall provide .......... with an opportunity to clarify and facilitate the resolution of the question or inconsistency.  Such an opportunity will be provided before a request for access, unless the Agency considers that delay in access would prejudice

the purpose for which the access is sought.  In any event, the Agency shall not draw any conclusions about the question or inconsistency until .......... has been provided with such an opportunity.

MAP article 4(e)

COMPLIMENTARY ACCESS

 Unless otherwise agreed to by .........., access shall only take place during regular working hours.

MAP Article 4(f)

COMPLIMENTARY ACCESS

 .......... shall have the right to have Agency inspectors accompanied during their access by representatives of .........., provided that the inspectors shall not thereby be delayed or otherwise impeded in the exercise of their

functions.

MAP article 5

COMPLIMENTARY ACCESS

MAP Article 5 (a)

COMPLIMENTARY ACCESS

(Parts (i) (ii) and (iii)

 (i) Any place on a site;

(ii) Any location identified by .......... under Article 2.a.(v)-(viii);

(iii) Any decommissioned facility or decommissioned location outside

facilities where nuclear material was customarily used

MAP article 5(b)

COMPLIMENTARY ACCESS

 Any location identified by .......... under Article 2.a.(i), Article 2.a.(iv), Article 2.a.(ix)(b), or Article 2.b, other than those referred to in paragraph a.(i) above, provided that if .......... is unable to provide such access, ..........

shall  make every reasonable effort to satisfy Agency requirements, without delay, through other means.

MAP article 5(c)

COMPLIMENTARY ACCESS

 Any location specified by  the Agency, other than locations referred to in paragraphs a. and b.  above, to carry out location-specific environmental sampling, provided that if .......... is unable to provide such access, .......... shall  make every reasonable effort to satisfy Agency requirements, without delay, at adjacent locations or through other means.

MAP Article 6

COMPLIMENTARY ACCESS

 When implementing Article 5, the Agency may carry out the following activities: (a, b, c & d).  

MAP article 6(a) 

COMPLIMENTARY ACCESS

 For access in accordance with Article 5.a.(i) or (iii): visual observation; collection of environmental samples; utilization of radiation detection and measurement devices; application of seals and other identifying and tamper indicating devices specified in Subsidiary Arrangements; and other objective measures which have been demonstrated to be technically feasible and the use of which has been  agreed by the Board of Governors (hereinafter referred to as the "Board") and following consultations between the Agency and ..........

MAP article 6(b)

COMPLIMENTARY ACCESS

For access in accordance with Article 5.a.(ii): visual observation; item counting of  nuclear material; non-destructive measurements and sampling; utilization of radiation detection and measurement devices;

examination of  records relevant to the quantities, origin and disposition of the material; collection of environmental samples; and other objective measures which have been demonstrated to be technically feasible and the use of which has been  agreed by the Board and following consultations between the Agency and ...........

MAP article 6(c)

COMPLIMENTARY ACCESS

 For access in accordance with Article 5.b.: visual observation; collection of environmental samples; utilization of radiation detection and measurement

devices; examination of safeguards relevant production and shipping records; and other objective measures which have been demonstrated to be technically feasible and the use of which has been  agreed by the Board and following consultations between the Agency and ..........

MAP article 6 (d)

COMPLIMENTARY ACCESS

 For access in accordance with Article 5.c.: collection of environmental samples and, in the event the results do not resolve the question or inconsistency at the location specified by the Agency pursuant to Article 5.c., utilization at that location of visual observation, radiation detection

and measurement devices, and, as agreed by .......... and the Agency, other objective measures.

MAP article 7

COMPLIMENTARY ACCESS

(a, b, & c)

 (a) Upon request by .........., the Agency and .......... shall  make arrangements for managed access under this Protocol  in order to prevent the dissemination of proliferation sensitive information, to meet safety or

physical protection requirements, or to protect proprietary or commercially sensitive information.  Such arrangements shall not preclude the Agency from conducting activities necessary to provide credible assurance of the absence of undeclared  nuclear material and activities at the location in question, including the resolution of  a question relating to the correctness and completeness of the information referred to in Article 2 or of an inconsistency relating to that information.

(b) ..........  may, when providing the information referred to in Article 2,

inform the Agency of the places at a  site or location at which managed

access may be applicable.

(c) Pending the entry into force of any necessary Subsidiary Arrangements,

......... may have recourse to managed access consistent with the provisions 

of paragraph a. above

MAP article 8

COMPLIMENTARY ACCESS

Nothing in this Protocol shall preclude .......... from offering the Agency access to locations  in addition to those referred to in Articles 5 and 9  or from

requesting the Agency to conduct verification activities at a particular location. The Agency shall, without delay, make every reasonable effort to act upon such a request.

MAP Article 9

COMPLIMENTARY ACCESS

..........shall provide the Agency with access to locations specified by the  Agency to carry out wide-area environmental sampling, provided that if .......... is

unable to provide such access it shall make every reasonable effort to satisfy Agency requirements at alternative locations.  The Agency shall not seek such

access until the use of  wide-area environmental sampling and the procedural arrangements therefor have been approved by the Board and following

consultations between the Agency and ..........

MAP Article 10

COMPLIMENTARY ACCESS

(text and parts a, b, & c)

The Agency shall inform .......... of:

a. The activities carried out under this Protocol, including those in respect of any questions or inconsistencies the Agency had brought to the attention of .........., within sixty days of the activities being carried out by the Agency. 

b. The results of activities in respect of any questions or inconsistencies the

Agency had brought to the attention of .........., as soon as possible but in any case within thirty days of the results being established by the Agency.

c. The conclusions it has drawn from its activities under this Protocol. The conclusions shall be provided annually.

MAP article 11 (a)

DESIGNATION OF AGENCY INSPECTORS

(parts i and ii)

(i) The Director General shall notify .......... of the Board's approval of any Agency official as a safeguards inspector. Unless ..........advises the Director General of its rejection of such an official as

an inspector for .......... within three months of receipt of notification of the Board's approval, the inspector so notified to ; ........... shall be considered designated to ..........

(ii) The Director General, acting in response to a request by .......... or on his own initiative, shall immediately inform .......... of the withdrawal of the designation of any official as an inspector for .......... .

MAP article 11(b)

DESIGNATION OF AGENCY INSPECTORS

 A notification referred to in paragraph a. above shall be deemed to be received by .......... seven days after the date of the transmission by registered mail of the notification by the Agency to .......... .

MAP article 12

VISAS

..........shall, within one month of the receipt of a request therefor, provide the designated inspector specified in the request with appropriate multiple entry/exit and/or transit visas, where required, to enable the inspector to enter and remain on the territory of .......... for the purpose of carrying out his/her functions.  Any visas required shall be valid for at least one year and shall be renewed, as required, to cover the duration of the inspector's designation to .......... 

MAP article 13

SUBSIDIARY ARRANGEMENTS

(a & b)

a. Where .......... or the Agency indicates that it is necessary to specify in Subsidiary Arrangements how measures laid down in this Protocol are to be applied, .......... and the Agency shall agree on such Subsidiary

Arrangements  within ninety days of  the entry into force of this Protocol or, where the indication of the need for such Subsidiary Arrangements is made after the entry into force of this Protocol, within ninety days of the date of such indication.

b. Pending the entry into force of any necessary Subsidiary Arrangements, the Agency shall be entitled to apply the measures laid down in this Protocol.

MAP article 14 (a)

COMMUNICATIONS SYSTEMS

a. .......... shall permit and protect free communications by the Agency for official purposes between Agency inspectors in .......... and Agency Headquarters and/or Regional Offices, including attended and unattended transmission of information generated by Agency containment and/or surveillance or measurement devices.  The Agency shall have, in consultation with .........., the right to make use of internationally established systems of direct communications, including satellite systems and other forms of telecommunication, not in use in ...........    At the request of .......... or the Agency, details of the implementation of this paragraph with respect to the attended or unattended transmission of information generated by Agency containment and/or surveillance or measurement devices shall be specified in the Subsidiary Arrangements.

MAP article 14(b)

COMMUNICATIONS SYSTEMS

b. Communication and transmission of information as provided for in paragraph a. above shall take due account of the need to protect proprietary or commercially sensitive information or design information which .......... regards as being of particular sensitivity.

MAP article 15 (a)

PROTECTION OF CONFIDENTIAL INFORMATION

 The Agency shall maintain a stringent regime to ensure effective protection against disclosure of commercial, technological and industrial secrets and other confidential information coming to its knowledge, including such information coming to the Agency's knowledge in the

implementation of this Protocol.

MAP Article 15(b)

PROTECTION OF CONFIDENTIAL INFORMATION

(text and parts i, ii and iii)

b. The regime referred to in paragraph a. above shall include, among others, provisions relating to:

(i) General principles and associated measures for the handling of confidential information;

(ii) Conditions of staff employment relating to the protection of confidential information;13

(iii) Procedures in cases of breaches or alleged breaches of confidentiality.

MAP article 15(c)

PROTECTION OF CONFIDENTIAL INFORMATION

 The regime referred to in paragraph a. above shall be approved and periodically reviewed by the Board.

MAP article 16 (a & b)

ANNEXES

a. The Annexes to this Protocol shall be an integral part thereof. Except for the purposes of amendment of the Annexes, the term "Protocol" as used in this instrument means the Protocol and the Annexes together.

b. The list of activities specified in Annex I, and the list of equipment and material specified in Annex II, may be amended by the Board upon the advice of an open-ended working group of experts established by the Board.  Any such amendment shall take effect four months after its adoption by the Board.

MAP article 17 (a)

ENTRY INTO FORCE

(* footnote)

a. This Protocol shall enter into force on the date on which the Agency receives from .......... written notification that ..........'s statutory and/or constitutional requirements for entry intoforce have been met. OR* upon signature by the representatives of .......... and the Agency.

* The choice of alternative depends on the preference of the State concerned according to its internal

legal requirements

MAP article 17(b)

ENTRY INTO FORCE

b. .......... may, at any date before this Protocol enters into force, declare that it will apply this Protocol provisionally.

MAP article 17 (c)

ENTRY INTO FORCE

c. The Director General shall promptly inform all Member States of the Agency of any declaration of provisional application of, and of the entry into force of, this Protocol.

MAP Article 18

DEFINITIONS

For the purpose of this Protocol:

MAP Article 18 (a)

DEFINITIONS

Nuclear fuel cycle-related research and development activities means those activities which are specifically related to any process or system development aspect of any of the following:

-  conversion of nuclear material, -  enrichment of nuclear material, -  nuclear fuel fabrication, -  reactors, -  critical facilities, -  reprocessing of nuclear fuel,

- processing (not including repackaging or conditioning not involving the separation of elements, for storage or disposal) of intermediate or high-level waste containing plutonium, high enriched uranium or uranium-233,

but do not include activities related to theoretical or basic scientific research or to research and development on industrial radioisotope applications, medical, hydrological and agricultural applications, health and environmental effects and improved maintenance.

MAP Article 18 (b)

DEFINITIONS

Site means that area delimited by .......... in the relevant design information for a  facility, including a  closed-down facility, and in the relevant information on a  location outside facilities where  nuclear material is customarily used, including a  closed-down location outside facilities where  nuclear material was customarily used (this is limited to locations with hot cells or where activities related to conversion,

enrichment, fuel fabrication or reprocessing were carried out).    It shall also include all installations,  co-located with the  facility or location, for the provision or use of essential services, including: hot cells for processing irradiated materials not containing  nuclear material; installations for the treatment, storage and disposal of waste;  and buildings associated with specified activities identified by .......... under Article 2.a.(iv) above.

MAP Article 18 (c)

DEFINITIONS

Decommissioned facility  or decommissioned location outside facilities means an installation or location at which residual structures and equipment essential for its use have been removed or rendered inoperable so that it is not used to store and can no longer be used to handle, process or utilize nuclear material.

MAP Article 18 (d)

DEFINITIONS

 Closed-down facility  or closed-down location outside facilities  means an installation or location where operations have been stopped and the nuclear material removed but which has not been decommissioned.

MAP article 18(e)

DEFINTIONS

High enriched uranium means uranium containing 20 percent or more of the isotope uranium-235.

Map article 18 (f)

DEFINITIONS

 Location-specific environmental sampling means the collection of environmental samples (e.g., air, water, vegetation, soil, smears) at, and in the immediate vicinity of, a location specified by the Agency for the purpose of assisting the Agency to draw conclusions about the absence of undeclared nuclear material or nuclear activities at the specified location. 

MAP article 18 (g)

DEFINITIONS

 Wide-area environmental sampling means the collection of environmental samples (e.g., air, water, vegetation, soil, smears) at a set of locations specified by the Agency for the purpose of assisting the Agency to draw conclusions about the absence of undeclared  nuclear material or nuclear activities over a wide area.

MAP article 18 (h)

DEFINITIONS

 Nuclear material means any source or any special fissionable material as defined in Article XX of the Statute.  The term source material shall not be

interpreted as applying to ore or ore residue.  Any determination by the Board under Article XX of the Statute of the Agency after the entry into force of this Protocol which adds to the materials considered to be source material or special fissionable material shall have effect under this Protocol only upon acceptance by ..........

MAP article 18 (i)

DEFINITIONS

(term, parts i and ii)

 Facility means:

(i) A reactor, a critical facility, a conversion plant, a fabrication plant, a reprocessing plant, an isotope separation plant or a separate storage installation;  or

(ii) Any location where nuclear material in amounts greater than one effective kilogram is customarily used.

MAP article 18 (j)

DEFINITIONS

 Location outside facilities means any installation or location, which is not a facility, where  nuclear material is customarily used in amounts of one effective kilogram or less.

MAP ANNEX  I (i)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

(text and 2 definitions)

(i) The manufacture of centrifuge rotor tubes or the assembly of gas centrifuges. 

Centrifuge rotor tubes means thin-walled cylinders as described in entry 5.1.1(b) of Annex II.

Gas centrifuges means centrifuges as described in the Introductory Note to entry 5.1 of Annex II

MAP ANNEX  I (ii)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL.

(text & 1 definition)

(ii) The manufacture of diffusion barriers.

Diffusion barriers means thin, porous filters as described in entry 5.3.1(a) of Annex II.

MAP ANNEX  I (iii)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

(text & 1 definition)

(iii) The manufacture or assembly of laser-based systems.

Laser-based systems means systems incorporating those items as described in entry 5.7 of Annex II.

MAP ANNEX  I (iv)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

(text & 1 definition)

The manufacture or assembly of Electromagnetic isotope separators. 

Electromagnetic isotope separators  means those items referred to in entry 5.9.1 of Annex II containing ion sources as described in 5.9.1(a) of Annex II

MAP ANNEX  I (v)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

 The manufacture or assembly of columns or extraction equipment.

Columns or  extraction equipment means those items as described in entries 5.6.1, 5.6.2, 5.6.3, 5.6.5, 5.6.6, 5.6.7 and 5.6.8 of Annex II

MAP ANNEX  I (vi)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

 The manufacture of aerodynamic separation nozzles or vortex tubes.

Aerodynamic separation nozzles or vortex tubes means separation nozzles and vortex tubes as described respectively in entries 5.5.1 and 5.5.2 of Annex II

MAP ANNEX  I (vii)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

 The manufacture or assembly of uranium plasma generation systems.

Uranium plasma generation systems means systems for the generation of uranium plasma as described in entry 5.8.3 of Annex II

 The manufacture of zirconium tubes.

Zirconium tubes means tubes as described in entry 1.6 of Annex II

MAP ANNEX  I (ix)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

The manufacture or upgrading of heavy water or deuterium. Heavy water or deuterium means deuterium, heavy water (deuterium oxide) and any other deuterium compound in which the ratio of deuterium to hydrogen atoms exceeds 1:5000.

MAP ANNEX  I (x)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

 The manufacture of nuclear grade graphite.

Nuclear grade graphite means graphite having a purity level better than 5 parts per million boron equivalent and with a density greater than 1.50 g/cm³.

 The manufacture of flasks for irradiated fuel.

A flask for irradiated fuel means a vessel for the transportation and/or storage of  irradiated fuel which provides chemical, thermal and radiological protection, and dissipates decay heat during handling, transportation and storage.

MAP ANNEX  I (xii)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

 The manufacture of reactor control rods.

Reactor control rods means rods as described in entry 1.4 of Annex I

MAP ANNEX  I (xiii)

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE PROTOCOL

 The manufacture of criticality safe tanks and vessels.

Criticality safe tanks and vessels means those items as described in entries 3.2 and 3.4 of Annex II.

 The manufacture of irradiated fuel element chopping machines.

Irradiated fuel element chopping machines means equipment as described in entry 3.1 of Annex II.

 The construction of hot cells.

Hot cells means a cell or interconnected cells totalling at least 6m in volume with shielding equal to or greater than the equivalent of 0.5 m of concrete, with a density of 3.2 g/cm³ or greater, outfitted with equipment for remote

operations

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)*

(Footnote only)

This is the list which the Board agreed at its meeting on 24 February 1993 would be used for the purpose of the voluntary reporting scheme, as subsequently amended by the Board.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

1.  Reactors and equipment therefor (1.1)

 Complete nuclear reactors

Nuclear reactors capable of operation so as to maintain a controlled selfsustaining fission chain reaction, excluding zero energy reactors, the latter being defined as reactors with a designed maximum rate of production of plutonium not exceeding 100 grams per year.

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. It is not intended to exclude reactors which could reasonably be capable of modification to produce significantly more than 100 grams of plutonium per year. Reactors designed for sustained operation at significant power levels, regardless of their capacity for plutonium production, are not considered as "zero energy reactors"

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

1.  Reactors and equipment therefor

1.2 Reactor Pressure Vessels

 Reactor pressure vessels

Metal vessels, as complete units or as major shop-fabricated parts therefor, which are especially designed or prepared to contain the core of a nuclear reactor as defined in paragraph 1.1. above and are capable of withstanding the operating pressure of the primary coolant.

Explanatory note

A top plate for a reactor pressure vessel is covered by item 1.2. as a major shop-fabricated part of a pressure vessel. Reactor internals (e.g. support columns and plates for the core and other vessel internals, control rod guide tubes, thermal shields, baffles, core grid plates, diffuser plates, etc.) are normally supplied by the reactor supplier. In some cases, certain internal support components are included in the fabrication of the pressure vessel. These items are sufficiently critical to the safety and reliability of the operation of the reactor (and, therefore, to the guarantees and liability of the reactor supplier), so that their supply, outside the basic supply arrangement for the reactor itself, would not be common practice. Therefore, although the separate supply of these unique, especially designed and prepared, critical, large and expensive items would not necessarily be considered as falling outside the area of concern, such a mode of supply is considered unlikely.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

1.  Reactors and equipment therefor

1.3  Reactor fuel charging and discharging machine

Manipulative equipment especially designed or prepared for inserting or removing fuel in a nuclear reactor as defined in paragraph 1.1. above capable of on-load operation or employing technically sophisticated

positioning or alignment features to allow complex off-load  fuelling operations such as those in which direct viewing of or access to the fuel is not normally available.

ANNEX  II

Rods especially designed or prepared for the control of the reaction rate in a nuclear reactor as defined in paragraph 1.1. above.

EXPLANATORY NOTE

This item includes, in addition to the neutron absorbing part, the support or suspension structures therefor if supplied separately.

ANNEX  I

LIST OF ACTIVITIES REFERRED TO IN ARTICLE 2.a.(iv) OF THE

 PROTOCOL

(List All Activities)

(i) The manufacture of centrifuge rotor tubes or the assembly of gas centrifuges.

(ii) The manufacture of diffusion barriers.

(iii) The manufacture or assembly of laser-based systems.

(iv) The manufacture or assembly of electromagnetic isotope separators.

(v) The manufacture or assembly of columns or extraction equipment.

(vi) The manufacture of aerodynamic separation nozzles or vortex tubes.

(vii) The manufacture or assembly of uranium plasma generation systems.

(viii) The manufacture of zirconium tubes.

(ix) The manufacture or upgrading of heavy water or deuterium.

(x) The manufacture of nuclear grade graphite.

(xi) The manufacture of flasks for irradiated fuel.

(xii) The manufacture of reactor control rods.

(xiii) The manufacture of criticality safe tanks and vessels.

(xiv) The manufacture of irradiated fuel element chopping machines.

(xv) The construction of hot cells

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

1.  Reactors and equipment therefor

1.5. Reactor pressure tube

Tubes which are especially designed or prepared to contain fuel elements and the primary coolant in a reactor as defined in paragraph 1.1. above at an operating pressure in excess of 5.1 MPa (740 psi).

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

1.  Reactors and equipment therefor

1.6. Zirconium tube

Zirconium metal and alloys in the form of tubes or assemblies of tubes, and in quantities exceeding 500 kg in any period of 12 months, especially designed or prepared for use in a reactor as defined in paragraph 1.1. above, and in which the relation of hafnium to zirconium is less than 1:500 parts by weight.

Pumps 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 may include 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 NC-1 or equivalent standards

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

2. Non-nuclear materials for reactors

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 1:5000 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

2. Non-nuclear materials for reactors

2.2. Nuclear grade graphite.

(Defintion & Note)

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 3 x 10

4 kg (30 metric tons) for any one recipient country in any period of 12 months.

NOTE: For the purpose of reporting, the Government will determine whether or not the exports of graphite meeting the above specifications are for nuclear

reactor use

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

3.  Plants for the reprocessing of irradiated fuel elements, and equipment

especially designed or prepared therefor

(Introductory Note, 1st Paragraph)

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.

ANNEX  II

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).

Items of equipment that are considered to fall within the meaning of the

phrase "and equipment especially designed or prepared" for the reprocessing

of irradiated fuel elements include:

ANNEX  II

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. 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

3.  Plants for the reprocessing of irradiated fuel elements, and equipment

especially designed or prepared therefor

3.2. Dissolvers

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. 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

3.  Plants for the reprocessing of irradiated fuel elements, and equipment

especially designed or prepared therefor

3.3. Solvent extractors and solvent extraction equipment.

Solvent extractors both receive the solution of irradiated fuel from thedissolvers 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. 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

3.  Plants for the reprocessing of irradiated fuel elements, and equipment

especially designed or prepared therefor

3.4. Chemical holding or storage vessels (part I: Three streams)

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 uraniumoxide. 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.

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 vesse

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

3.  Plants for the reprocessing of irradiated fuel elements, and equipment

especially designed or prepared therefor

3.5. Plutonium nitrate to oxide conversion syste

In most reprocessing facilities, this final process involves the conversion of the plutonium nitrate solution to plutonium dioxide. 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. Complete systems especially designed or prepared for the conversion of plutonium nitrate to plutonium oxide, in particular adapted so as to avoid criticality and radiation effects and to minimize toxicity hazards.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

3.  Plants for the reprocessing of irradiated fuel elements, and equipment

especially designed or prepared therefor

3.6. Plutonium oxide to metal production syste

This process, which could be related to a reprocessing facility, 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, productAII/10 handling, ventilation, waste management and process control. Complete systems especially designed or prepared for the production of plutonium metal, in particular adapted so as to avoid criticality and

radiation effects and to minimize toxicity hazards.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

4. Plants for the fabrication of fuel element

A "plant for the fabrication of fuel elements" includes the equipment:

(a) Which normally comes in direct contact with, or directly processes, or controls, the production flow of nuclear material, or

(b) Which seals the nuclear material within the cladding

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

(preliminary text)

Items of equipment that are considered to fall within the meaning of the phrase "equipment, other than analytical instruments, especially designed or prepared" for the separation of isotopes of uranium include:

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1 Gas centrifuges and assemblies and components especially designed or 

The gas centrifuge normally consists of a thin-walled cylinder(s) of between 75 mm (3 in) and 400 mm (16 in) 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 3 separate channels, of which 2 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.1. Rotating components

(b) Rotor tubes

(b) Rotor tubes: Especially designed or prepared thin-walled cylinders with thickness of 12 mm (0.5 in) or less, a diameter of between 75 mm (3 in) and 400 mm (16

in), and manufactured from one or more of the high strength to density ratio materials described in the EXPLANATORY NOTE to this Section.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.1. Rotating components

 (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 (0.12 in) or less, a diameter of between 75 mm (3 in) and 400 mm (16 in), having a convolute, and manufactured from one of the high strength to density ratio materials described in the

EXPLANATORY NOTE to this Section.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.1. Rotating components

(d) Baffles

Disc-shaped components of between 75 mm (3 in) and 400 mm (16 in) 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.1. Rotating components

(e) Top caps/Bottom caps

Disc-shaped components of between 75 mm (3 in) and 400 mm (16 in) 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

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.1. Rotating components

Explanatory note (introductory sentend and a, b & c)

The materials used for centrifuge rotating components are:

(a) Maraging steel capable of an ultimate tensile strength of 2.05 x 10⁹ N/m² (300,000 psi) or more;

(b) Aluminium alloys capable of an ultimate tensile strength of 0.46 x 10⁹ N/m²  (67,000 psi) or more;

(c) Filamentary materials suitable for use in composite structures and having a specific modulus of 12.3 x 10⁶m or greater and a specific ultimate tensile strength of 0.3 x 10⁶  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

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.2. Static components

(a) Magnetic suspension bearings

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 (120,000 in CGS units) or more, or a remanence of 98.5% or more, or an energy product of greater than 80 kJ/m³(10⁷ gauss-oersteds). 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 0.004 in) or that homogeneity of the material of the magnet is specially called for

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.2. Static components

(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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.2. Static components

(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 (3 in) to 400 mm (16 in) internal diameter, 10 mm (0.4 in) 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 (0.08 in) or more in depth.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.2. Static components

(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 in the frequency range of 600 - 2000 Hz and a power range

of 50 - 1000 VA. The stators consist of  multi-phase windings on a laminated low loss iron core comprised of thin layers typically 2.0 mm (0.08 in) thick or less.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.2. Static components

(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 (1.2 in) 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 tubes. The housings are made of or protected by materials resistant to corrosion by UF₆ 

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.1.2. Static components

(f) Scoops

Especially designed or prepared tubes of up to 12 mm (0.5 in) internal diameter 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. The tubes are made of or protected by materials resistant to corrosion by UF₆

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.2. Especially designed or prepared auxiliary systems, equipment and components for gas centrifuge enrichment plant.

INTRODUCTORY NOTE

The auxiliary systems, equipment and components for a gas centrifuge enrichment plant are the systems of plant needed to feed UF6 to the centrifuges, to link the individual centrifuges to each other to form cascades (or stages) to allow for progressively higher enrichments and to  extract the 'product' and 'tails' UF6 from the centrifuges, together with the equipment required to drive the centrifuges or to control the plant. Normally UF₆ is evaporated from the solid using heated autoclaves and is distributed in gaseous form to the centrifuges by way of cascade header pipework. The 'product' and 'tails' UF₆ gaseous streams flowing from the centrifuges are also passed by way of cascade header pipework to cold traps (operating at about 203 K (-70o C)) where they are condensed prior to  onward transfer into suitable containers for transportation or storage. Because an enrichment plant consists of many thousands of centrifuges arranged in cascades there are many kilometers of cascade header pipework, incorporating thousands of welds with a substantial amount of repetition of layout. The equipment, components and piping systems are fabricated to very high vacuum and cleanliness standards.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.2. Especially designed or prepared auxiliary systems, equipment and components for gas centrifuge enrichment plant.

5.2.1. Feed systems/product and tails withdrawal system

Especially designed or prepared process systems including:

Feed autoclaves (or stations), used for passing UF6 to the centrifuge

cascades at up to 100 kPa (15 psi) and at a rate of 1 kg/h or more;

Desublimers (or cold traps) used to remove UF6 from the cascades at

up to 3 kPa (0.5 psi) pressure. The desublimers are capable of being

chilled to 203 K (-70 oC) and heated to 343 K (70 oC); 'Product' and 'Tails' stations used for trapping UF6 into containers. This plant, equipment and  pipework is wholly made of or lined with UF6-

resistant materials (see EXPLANATORY NOTE to this section) and is

fabricated to very high vacuum and cleanliness standards.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.2. Especially designed or prepared auxiliary systems, equipment and components for gas centrifuge enrichment plant.

5.2.2. Machine header piping system

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 UF6-resistant materials (see EXPLANATORY  NOTE to this section) and is fabricated to very high vacuum and cleanliness

standards.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.2. Especially designed or prepared auxiliary systems, equipment and components for gas centrifuge enrichment plant.

5.2.3. UF6 mass spectrometers/ion source (opening sentence and 4 characteristics)

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of taking 'on-line' samples of feed, product or tails, from UF6 gas streams and having all of the following characteristics:

1. Unit resolution for atomic mass unit greater than 320;

2. Ion sources constructed of or lined with nichrome or monel or nickel

plated;

3. Electron bombardment ionization sources;

4. Having a collector system suitable for isotopic analysis

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.2. Especially designed or prepared auxiliary systems, equipment and components for gas centrifuge enrichment plant.

5.2.4. Frequency changers (opening sentence, 4 characteristics, and explanatory note)

Frequency  changers (also known as converters or  invertors) 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 output of 600 to 2000 Hz; 

2. High stability (with frequency control better than 0.1%); 

3. Low harmonic distortion (less than 2%); and 

4. An efficiency of greater than 80%. 

EXPLANATORY NOTE The items listed above either come into direct contact with the UF6 process gas or directly control the centrifuges and the passage of the gas from centrifuge to centrifuge and cascade to cascade. Materials resistant to corrosion by UF6 include stainless steel,  aluminium,aluminium alloys, nickel or alloys containing 60% or more nickel.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.3.  Especially designed or prepared assemblies and components for use in gaseous diffusion enrichment 

(Introductory Note)

In the gaseous diffusion method of uranium isotope separation, the main technological assembly is a special porous gaseous diffusion barrier, heat exchanger for cooling the gas (which is heated by the process of compression), seal valves and control valves, and pipelines. Inasmuch as gaseous diffusion technology uses uranium  hexafluoride (UF6), all equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must be made of materials that remain stable in contact with UF₆.  A gaseous diffusion facility requires a number of these assemblies, so that quantities can provide an important indication of end use.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.3.  Especially designed or prepared assemblies and components for use in gaseous diffusion enrichment 

5.3.1. Gaseous diffusion barrier ((a) & (b))

(a) Especially designed or prepared thin, porous filters, with a pore size of 100 - 1,000 Å (angstroms), a thickness of 5 mm (0.2 in) or less, and for tubular forms, a diameter of 25 mm (1 in) or less, made of metallic, polymer or ceramic materials resistant to corrosion by UF6, and

(b) especially prepared compounds or powders for the manufacture of

such filters. Such compounds and powders include nickel or alloys containing 60 per cent or more nickel,  aluminium oxide, or UF6-resistant fully fluorinated hydrocarbon polymers having a purity of 99.9 per cent or more, a particle size less than 10 microns, and a high degree of particle size uniformity, which are especially prepared for the manufacture of gaseousdiffusion barriers.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.3.  Especially designed or prepared assemblies and components for use in gaseous diffusion enrichment 

5.3.2. Diffuser housing

Especially designed or prepared hermetically sealed cylindrical vessels greater than 300 mm (12 in) in diameter and greater than 900 mm (35 in) in length, or rectangular vessels of comparable dimensions, which have an inlet connection and two outlet connections all of which are greater than 50 mm (2 in) in diameter, for containing the gaseous diffusion barrier, made of

or lined with UF6-resistant materials and designed for horizontal or vertical installation.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.3.  Especially designed or prepared assemblies and components for use in gaseous diffusion enrichment

5.3.3. Compressors and gas blowers

Especially designed or prepared axial, centrifugal, or positive displacement compressors, or gas blowers with a suction volume capacity of 1 m³/min or more of UF₆, and with a discharge pressure of up to several hundred  kPa (100 psi), designed for long-term operation in the UF6 environment with or without an electrical motor of appropriate power, as well as separate assemblies of such compressors and gas blowers. These compressors and gas blowers have a pressure ratio between 2:1 and 6:1 and are made of, or lined with, materials resistant to UF₆

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.3.  Especially designed or prepared assemblies and components for use in gaseous diffusion enrichment

5.3.4. 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 1000 cm³/min (60 in³/min).

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.3.  Especially designed or prepared assemblies and components for use in gaseous diffusion enrichment

5.3.5. Heat exchangers for cooling UF₆

Especially designed or prepared heat exchangers made of or lined with UF6- resistant materials (except stainless steel) or with copper or any combination of those metals, and intended for a leakage pressure change rate of less than 10 Pa (0.0015 psi) per hour under a pressure difference of 100 kPa (15 psi).

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.4. Especially designed or prepared auxiliary systems, equipment and components for use in gaseous diffusion enrichment

(Introductory Note, Paragraph 1)

The auxiliary systems, equipment and components for gaseous diffusion enrichment plants are the systems of plant needed to feed UF₆ to the gaseous diffusion assembly, to link the individual assemblies to each other to form cascades (or stages) to allow for progressively higher enrichments and to extract the 'product' and 'tails' UF₆ from the diffusion cascades. Because of the high inertial properties of diffusion cascades, any interruption in their operation, and especially their shut-down, leads to serious consequences. Therefore, a strict and constant maintenance of 

vacuum in all technological systems, automatic protection from accidents, and precise automated regulation of the gas flow is of importance in a,gaseous diffusion plant. All this leads to a need to equip the plant with a large number of special measuring, regulating and controlling systems.

Normally UF6 is evaporated from cylinders placed within autoclaves and is distributed in gaseous form to the entry point by way of cascade header pipework. The 'product' and 'tails' UF₆ gaseous streams flowing from exit points are passed by way of cascade header pipework to either cold traps or to compression stations where the UF₆ gas is liquefied prior to onward transfer into suitable containers for transportation or storage. Because a gaseous diffusion enrichment plant consists of a large number of gaseous diffusion assemblies arranged in cascades, there are many kilometers of cascade header pipework, incorporating thousands of welds with substantial amounts of repetition of layout. The equipment, components and piping systems are fabricated to very high vacuum and cleanliness standards.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.4. Especially designed or prepared auxiliary systems, equipment and  components for use in gaseous diffusion enrichment

5.4.1. Feed systems/product and tails withdrawal system (4 types)

Especially designed or prepared process systems, capable of operating at pressures of 300 kPa (45 psi) or less, including: Feed autoclaves (or systems), used for passing UF₆ to the gaseous diffusion cascades;

Desublimers (or cold traps) used to remove UF₆ from diffusion cascades; Liquefaction stations where UF₆ gas from the cascade is compressed and cooled to form liquid UF₆; 'Product' or 'tails' stations used for transferring UF₆ into containers.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.4. Especially designed or prepared auxiliary systems, equipment and  components for use in gaseous diffusion enrichment

5.4.2. Header piping system

Especially designed or prepared piping systems and header systems for handling UF₆ within the gaseous diffusion cascades. This piping network is normally of the "double" header system with each cell connected to each of the headers.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.4. Especially designed or prepared auxiliary systems, equipment and  components for use in gaseous diffusion enrichment

5.4.3. Vacuum systems ( (a) & (b))

(a) Especially designed or prepared large vacuum manifolds, vacuum headers and vacuum pumps having a suction capacity of 5 m³ /min (175 ft³/min) or more.

(b) Vacuum pumps especially designed for service in UF₆-bearing atmospheres made of, or lined with,  aluminium, nickel, or alloys bearing more than 60% nickel. These pumps may be either rotary or positive, may have displacement and fluorocarbon seals, and may have special working fluids present.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.4. Especially designed or prepared auxiliary systems, equipment and  components for use in gaseous diffusion enrichment

5.4.4. Special shut-off and control valves

Especially designed or prepared manual or automated shut-off and control bellows valves made of UF6-resistant materials with a diameter of 40 to 1500 mm (1.5 to 59 in) for installation in main and auxiliary systems of gaseous diffusion enrichment plants.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.4. Especially designed or prepared auxiliary systems, equipment and  components for use in gaseous diffusion enrichment

5.4.5. UF₆ mass spectrometers/ion sources (introductory sentence, 4 characteristics & Explanatory Note)

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of taking "on-line" samples of feed, product or tails, from UF₆ gas streams and having all of the following characteristics:

1. Unit resolution for atomic mass unit greater than 320;

2. Ion sources constructed of or lined with nichrome or monel or nickel

plated;

3. Electron bombardment ionization sources;

4. Collector system suitable for isotopic analysis.

EXPLANATORY NOTE: The items listed above either come into direct contact with the UF6 process

gas or directly control the flow within the cascade. All surfaces which come into contact with the process gas are wholly made of, or lined with, UF₆- resistant materials. For the purposes of the sections relating to gaseous diffusion items the materials resistant to corrosion by UF₆ include  stainless steel,  aluminium,  aluminium alloys,  aluminium oxide, nickel or alloys containing 60% or more nickel and UF6-resistant fully fluorinated hydrocarbon polymers.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

In aerodynamic enrichment processes, a mixture of gaseous UF₆ and light gas (hydrogen or helium) is compressed and then passed through separating elements wherein isotopic separation is accomplished by the generation of high centrifugal forces over a curved-wall geometry. Two processes of this type have been successfully developed: the separation nozzle process and the vortex tube process. For both processes the main components of a separation stage include cylindrical vessels housing the special separation elements (nozzles or vortex tubes), gas compressors and heat exchangers to remove the heat of compression. An aerodynamic plant requires a number of these stages, so that quantities can provide an important indication of end use. Since aerodynamic processes use UF₆, all equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must be made of materials that remain stable in contact with UF₆.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

(Explanatory Note)

The items listed in this section either come into direct contact with the UF₆ process gas or directly control the flow within the cascade. All surfaces which come into contact with the process gas are wholly made of or protected by UF₆-resistant materials. For the purposes of the section relating to aerodynamic enrichment items, the materials resistant to corrosion by UF₆ include copper, stainless steel, aluminium, aluminium alloys, nickel or alloys containing 60% or more nickel and UF₆-resistant fully fluorinated hydrocarbon polymers.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.1. 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 (typically 0.1 to 0.05 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.2. Vortex tubes (def + Explanatory note)

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, having a diameter of between 0.5 cm and 4 cm, a length to diameter ratio of 20:1 or less and with one or more tangential inlets. The tubes may be equipped with nozzle-type 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.3. Compressors and gas blowers (def + Explanatory note)

Especially designed or prepared axial, centrifugal or positive displacement compressors or gas blowers made of or protected by materials resistant to corrosion by UF₆ and with a suction volume capacity of 2 m³ /min or more of UF₆/carrier gas (hydrogen or helium) mixture.

EXPLANATORY NOTE

These compressors and gas blowers typically have a pressure ratio between 1.2:1 and 6:1.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.4. 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.5. Heat exchangers for gas cooling

Especially designed or prepared heat exchangers made of or protected by materials resistant to corrosion by UF_6.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.6. Separation element housing (Def + Explanatory Note)

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.

EXPLANATORY NOTE

These housings may be cylindrical vessels greater than 300 mm in diameter and greater than 900 mm in length, or may be rectangular vessels of comparable dimensions, and may be designed for horizontal or vertical installation.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.7. Feed systems/product and tails withdrawal system

(Def + (a) (b) (c) & (d))

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

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.8. Header piping system

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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.9. Vacuum systems and pumps ((a) & (b))

(a) Especially designed or prepared vacuum systems having a suction capacity of 5 m³ /min or more, consisting of vacuum manifolds, vacuum headers and vacuum pumps, and designed for service in UF₆-bearing atmospheres,

(b) 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.10. Special shut-off and control valves

Especially designed or prepared manual or automated shut-off and control bellows valves made of or protected by materials resistant to corrosion by UF₆ with a diameter of 40 to 1500 mm for installation in main and auxiliary

systems of aerodynamic enrichment plants.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.11. UF₆ mass spectrometers/ion sources (def + 4 characteristics)

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of taking 'on-line' samples of feed, 'product' or 'tails', from UF₆ gas streams and having all of the following characteristics:

1. Unit resolution for mass greater than 320;

2. Ion sources constructed of or lined with nichrome or monel or nickel plated;

3. Electron bombardment ionization sources;

4. Collector system suitable for isotopic analysis.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.5. Especially designed or prepared systems, equipment and components

for use in aerodynamic enrichment plants

5.5.12. UF6/carrier gas separation system (def + Explanatory note: intro + parts a b c & d)

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  -120 o C or less, or

(b) Cryogenic refrigeration units capable of temperatures of -120  o 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 temperatures of -20o C or less

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

The slight difference in mass between the isotopes of uranium causes small changes in chemical reaction  equilibria that can be used as a basis for

separation of the isotopes. Two processes have been successfully developed:liquid-liquid chemical exchange and solid-liquid ion exchange

In the liquid-liquid chemical exchange process,  immiscible liquid phases (aqueous and organic) are countercurrently contacted to give the cascading effect of thousands of separation stages. The aqueous phase consists of uranium chloride in hydrochloric acid solution; the organic phase consists of an  extractant containing uranium chloride in an organic solvent. The contactors employed in the separation cascade can be liquid-liquid exchange columns (such as pulsed columns with sieve plates) or liquid centrifugal contactors. Chemical conversions (oxidation and reduction) are required at both ends of the separation cascade in order to provide for the reflux requirements at each end. A major design concern is to avoid contamination  of the process streams with certain metal ions. Plastic, plastic-lined (including use of fluorocarbon polymers) and/or glass-lined columns and piping are therefore used.

In the solid-liquid ion-exchange process, enrichment is accomplished by uranium adsorption/desorption on a special, very fast-acting, ion-exchange resin or adsorbent. A solution of uranium in hydrochloric acid and other chemical agents is passed through cylindrical enrichment columns containing packed beds of the adsorbent. For a continuous process, a reflux system is necessary to release the uranium from the adsorbent back into the liquid flow so that 'product' and 'tails' can be collected. This is accomplished with the use of suitable reduction/oxidation chemical agents that are fully regenerated in separate external circuits and that may be partially

regenerated within the isotopic separation columns themselves. The

presence of hot concentrated hydrochloric acid solutions in the process requires that the equipment be made of or protected by special corrosionresistant materials.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

Countercurrent liquid-liquid exchange columns having mechanical power input (i.e., pulsed columns with sieve plates, reciprocating plate columns, and columns with internal turbine mixers), especially designed or prepared for uranium enrichment using the chemical exchange process. For corrosionmresistance to concentrated hydrochloric acid solutions, these columns and their internals are made of or protected by suitable plastic materials (such as fluorocarbon polymers) or glass. The stage residence time of the columns is designed to be short (30 seconds or less)

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

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 made of or are lined with suitable plastic materials (such as fluorocarbon polymers) or are lined with glass. The stage residence time of the centrifugal  contactors is designed to be short (30 seconds or less).

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.6. Especially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plants  5.6.3.(a) Uranium reduction systems and equipment (Chemical exchange) (def +Explanatory note)

(b) Especially designed or prepared systems at the product end of the

cascade for taking the U⁴⁺ 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 U⁴⁺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 resin-impregnated graphite)

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.6. Especially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plants 5.6.4. 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 U⁶⁺ or U⁴⁺ to U³⁺ 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 U³⁺ include glass, fluorocarbon polymers,  polyphenyl sulfate or  polyether sulfone plastic-lined and resin-impregnated graphite.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.6. Especially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plants 5.6.5. Uranium oxidation systems (Chemical exchange) (Def + Explanatory note: intro sentence + a & b)

Especially designed or prepared systems for oxidation of U³⁺ to U⁴⁺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 U⁴⁺ 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

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.6. Especially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plants  5.6.6. 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 fibers. 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 physicallyAII/29 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 100 o C to 200 o C

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.6. Especially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plants 5.6.7. Ion exchange columns (Ion exchange)

Cylindrical columns greater than 1000 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 100 o C to 200  o C and pressures above 0.7 MPa (102 psia).

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.6. Especially designed or prepared systems, equipment and components for use in chemical exchange or ion exchange enrichment plants 5.6.8. Ion exchange reflux systems (Ion exchange) (a + b & Explanatory note)

(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.

EXPLANATORY NOTE

The ion exchange enrichment process may use, for example, trivalent titanium (Ti³⁺) as a reducing  cation in which case the reduction system would regenerate Ti³⁺ by reducing Ti⁴⁺. The process may use, for example, trivalent iron (Fe³⁺) as an oxidant in

which case the oxidation system would regenerate Fe³⁺

 by oxidizing Fe2⁺

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant. (Introductory Note & a b c & d)

Present systems for enrichment processes using lasers fall into two categories: those in which the process medium is atomic uranium vapor and those in which the process medium is the vapor of a uranium compound. Common nomenclature for such processes include: first category - atomic vapor laser isotope separation (AVLIS or SILVA); second category - molecular laser isotope separation (MLIS or MOLIS) and chemical reaction by isotope selective laser activation (CRISLA). The systems, equipment and components for laser enrichment plants embrace: (a) devices to feed uranium-metal vapor (for selective photo-ionization) or devices to feed the vapor of a uranium compound (for photo-dissociation or chemical activation); (b) 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 'product' and unaffected material as 'tails' in the second category; (c) process laser systems to selectively excite the uranium-235 species; and (d) feed preparation and product conversion equipment. The complexity of the spectroscopy of uranium atoms and compounds may require incorporation of any of a number of available laser technologies

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant. (Explanatory Note)

Many of the items listed in this section come into direct contact with uranium metal vapor or liquid or with process gas consisting of UF₆ or a mixture of UF₆ and other gases. All surfaces that come into contact with the uranium or UF₆ are wholly made of or protected by corrosion-resistant materials. For the purposes of the section relating to laser-based enrichment items, the materials resistant to corrosion by the vapor or liquid of uranium metal or uranium alloys include yttria-coated graphite and tantalum; and the materials resistant to corrosion by UF₆ include copper, stainless steel, aluminium,  aluminium alloys, nickel or alloys containing 60 % or more nickel and UF₆-resistant fully fluorinated hydrocarbon polymers.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.1. Uranium vaporization systems (AVLIS)

Especially designed or prepared uranium vaporization systems which contain high-power strip or scanning electron beam guns with a delivered power on the target of more than 2.5 kW/cm.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.2. Liquid uranium metal handling systems (AVLIS) (Def + Explanatory Note)

Especially designed or prepared liquid metal handling systems for molten uranium or uranium alloys, consisting of crucibles and cooling equipment for the crucibles.

EXPLANATORY NOTE

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 corrosion and heat resistance. Suitable materials include tantalum, yttria-coated graphite, graphite coated with other rare earth oxides or mixtures thereof.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.3. Uranium metal 'product' and 'tails' collector assemblies (AVLIS) (Def + Explanatory Note)

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 vapor 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.4. Separator module housings (AVLIS) (def + Explanatory Note)

Especially designed or prepared cylindrical or rectangular vessels for containing the uranium metal vapor source, the electron beam gun, and the 'product' and 'tails' collectors. 

EXPLANATORY NOTE

These housings have multiplicity of ports for electrical and water feedthroughs, laser beam windows, vacuum pump connections and instrumentation diagnostics and monitoring. They have provisions for opening and closure to allow refurbishment of internal components

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.5. Supersonic expansion nozzles (MLIS)

Especially designed or prepared supersonic expansion nozzles for cooling mixtures of UF₆ and carrier gas to 150 K or less and which are corrosion resistant to UF₆

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.6. Uranium pentafluoride product collectors (MLIS)

Especially designed or prepared uranium  pentafluoride (UF5) solid product collectors consisting of filter, impact, or cyclone-type collectors, or combinations thereof, and which are corrosion resistant to the UF₅/UF₆ environment

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.7. UF6/carrier gas compressors (MLIS)

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

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.8. Rotary shaft seals (MLIS)

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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.9. Fluorination systems (MLIS) (Def + Explanatory Note)

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 to MLIS units 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.

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

5. Plants for the separation of isotopes of uranium and equipment, otherthan analytical instruments, especially designed or prepared therefor

5.7. Especially designed or prepared systems, equipment and components for use in laser-based enrichment plant.

5.7.10. UF6 mass spectrometers/ion sources (MLIS) (Def + Characteristics 1, 2, 3 & 4)

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of taking 'on-line' samples of feed, 'product' or 'tails', from UF₆ gas

streams and having all of the following characteristics: