Shared Flashcard Set

Details

INFCIRC-540
M.A.Pro
226
Law
Post-Graduate
02/18/2011

Additional Law Flashcards

 


 

Cards

Term
MAP Preamble 1
Definition

 

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

 

Term
MAP Preamble 2
Definition

 

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

 

Term

 

 

MAP Article 1: 

 

RELATIONSHIP BETWEEN THE PROTOCOL AND THE SAFEGUARDS AGREEMENT

 

Definition

 

 

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.

 

Term

 

 

MAP Article 2 (a)

 

 

PROVISION OF INFORMATION

 

 

Definition

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

Term

 

 

MAP Article 2 (a) (i)

PROVISION OF INFORMATION

Definition

 

 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, .......... 

 

Term

MAP Article 2 a(ii)

PROVISION OF INFORMATION

Definition

 

 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.

 

Term

MAP Article 2 (a) (iii)

PROVISION OF INFORMATION

Definition

 

 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.

 

Term

 

MAP Article 2 (a) (iv)

PROVISION OF INFORMATION

Definition

 

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

 

Term

MAP Article 2 (a) (v)

PROVISION OF INFORMATION

Definition

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.

 

Term

MAP Article 2 (a) (vi)

PROVISION OF INFORMATION

Definition

 

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

 

Term

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

PROVISION OF INFORMATION

Definition

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.

 

Term

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

PROVISION OF INFORMATION

(Text, Parts 1 & 2)

Definition

 

  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;

 

Term

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

PROVISION OF INFORMATION

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

Definition

 

 

 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.

 

 

 

Term

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

PROVISION OF INFORMATION

(Text & Footnote)

Definition

 

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

 


 

Term

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

PROVISION OF INFORMATION

Definition

 

 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.

 

Term

MAP Article 2 (a) (viii)

PROVISION OF INFORMATION

Definition

 

 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.

 

Term

MAP Article 2 (a)(ix)

PROVISION OF INFORMATION

(Text and parts a & b)

Definition

 

 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 …………….. .”

 

Term

MAP Article 2 (a)(x)

PROVISION OF INFORMATION

Definition

 

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 ..........  .

 

Term

MAP Article 2 (b) 

PROVISION OF INFORMATION

Definition

 

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

 

Term

MAP Article 2 (b)(i)

PROVISION OF INFORMATION

Definition

 

 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.

 

Term

MAP Article 2 (b)(ii)

PROVISION OF INFORMATION

Definition

 

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.

 

Term

MAP Article 2 (c)

PROVISION OF INFORMATION

Definition

 

 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.

 

Term

MAP Article 3 (a)

PROVISION OF INFORMATION

Definition

 

 .......... 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.

 

Term

MAP Article 3 (b)

PROVISION OF INFORMATION

Definition

 

 .......... 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.

 

Term

MAP Article 3 (c)

PROVISION OF INFORMATION

Definition

 

 .......... 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.

 

Term

MAP Article 3 (d)

PROVISION OF INFORMATION

Definition

 

 .......... 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.

 

Term

MAP Article 3 (e)

PROVISION OF INFORMATION

Definition

 

 .......... 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.

 

Term

MAP Article 3 (f)

PROVISION OF INFORMATION

Definition

 

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

 

Term

MAP Article 3(g)

PROVISION OF INFORMATION

Definition

 

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

 

Term

MAP Article 4

COMPLIMENTARY ACCESS

Definition

 

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

 

Term

MAP Article 4 (a)

COMPLIMENTARY ACCESS

Definition

 

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

 

Term

MAP Article 4 (a)(i)

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP Article 4(a)(ii)

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP Article 4(a)(iii)

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP Article 4 (b) 

COMPLIMENTARY ACCESS

(parts i & ii)

Definition

 

 (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.

 

Term

MAP Article 4 (c)

COMPLIMENTARY ACCESS

Definition

 

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

 

Term

MAP Article 4 (d) 

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP article 4(e)

COMPLIMENTARY ACCESS

Definition

 

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

 

Term

MAP Article 4(f)

COMPLIMENTARY ACCESS

 

Definition

 

 .......... 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.

 

Term

MAP article 5

COMPLIMENTARY ACCESS

Definition
:shall provide the Agency with access to ..........
Term

MAP Article 5 (a)

COMPLIMENTARY ACCESS

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

Definition

 

 (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

 

Term

MAP article 5(b)

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP article 5(c)

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP Article 6

COMPLIMENTARY ACCESS

Definition

 

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

 

Term

MAP article 6(a) 

COMPLIMENTARY ACCESS

Definition

 

 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 ..........

 

Term

MAP article 6(b)

COMPLIMENTARY ACCESS

 

Definition

 

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 ...........

 

Term

MAP article 6(c)

COMPLIMENTARY ACCESS

 

Definition

 

 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 ..........

 

Term

MAP article 6 (d)

COMPLIMENTARY ACCESS

Definition

 

 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.

 

Term

MAP article 7

COMPLIMENTARY ACCESS

(a, b, & c)

Definition

 

 (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

 

Term

MAP article 8

COMPLIMENTARY ACCESS

Definition

 

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.

 

Term

MAP Article 9

COMPLIMENTARY ACCESS

Definition

 

..........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 ..........

 

Term

 

MAP Article 10

COMPLIMENTARY ACCESS

(text and parts a, b, & c)

Definition

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.

Term

MAP article 11 (a)

DESIGNATION OF AGENCY INSPECTORS

(parts i and ii)

Definition

(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 .......... .

Term

MAP article 11(b)

DESIGNATION OF AGENCY INSPECTORS

Definition

 

 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 .......... .

 

Term

MAP article 12

VISAS

Definition

..........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 .......... 

Term

MAP article 13

SUBSIDIARY ARRANGEMENTS

(a & b)

Definition

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.

Term

MAP article 14 (a)

COMMUNICATIONS SYSTEMS

Definition

 

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.



 

Term

MAP article 14(b)

COMMUNICATIONS SYSTEMS

Definition

 

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.

 

Term

MAP article 15 (a)

PROTECTION OF CONFIDENTIAL INFORMATION

Definition

 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.

Term

MAP Article 15(b)

PROTECTION OF CONFIDENTIAL INFORMATION

(text and parts i, ii and iii)

Definition

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.

Term

MAP article 15(c)

PROTECTION OF CONFIDENTIAL INFORMATION

Definition

 

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

 

Term

MAP article 16 (a & b)

ANNEXES

Definition

 

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.

 

Term

MAP article 17 (a)

ENTRY INTO FORCE

(* footnote)

Definition

 

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

Term

MAP article 17(b)

ENTRY INTO FORCE

Definition

 

 

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

 

Term

MAP article 17 (c)

ENTRY INTO FORCE

Definition

 

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.

 

Term

MAP Article 18

DEFINITIONS

Definition

 

 

For the purpose of this Protocol:

 

Term

MAP Article 18 (a)

DEFINITIONS

Definition

 

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.

 

Term

MAP Article 18 (b)

DEFINITIONS

Definition

 

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.

 

Term

MAP Article 18 (c)

DEFINITIONS

Definition

 

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.

 

Term

MAP Article 18 (d)

DEFINITIONS

Definition

 

 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.

 

Term

MAP article 18(e)

DEFINTIONS

Definition

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

Term

Map article 18 (f)

DEFINITIONS

Definition

 

 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. 

 

Term

MAP article 18 (g)

DEFINITIONS

Definition

 

 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.

 

Term

MAP article 18 (h)

DEFINITIONS

Definition

 

 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 ..........

 

Term

MAP article 18 (i)

DEFINITIONS

(term, parts i and ii)

Definition

 

 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.

 

Term

MAP article 18 (j)

DEFINITIONS

Definition

 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.

Term

MAP ANNEX  I (i)

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

(text and 2 definitions)

Definition

(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

Term

MAP ANNEX  I (ii)

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

(text & 1 definition)

Definition

(ii) The manufacture of diffusion barriers.

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

Term

MAP ANNEX  I (iii)

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

(text & 1 definition)

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.

Term

 

MAP ANNEX  I (iv)

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

(text & 1 definition)

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

 

Term

MAP ANNEX  I (v)

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

 

Definition

 

 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

 

Term

 

MAP ANNEX  I (vi)

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

 

Definition

 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

 

Term

MAP ANNEX  I (vii)

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

Definition

 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

Term

 

MAP ANNEX  I (viii)

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

 

Definition

 

 The manufacture of zirconium tubes.

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

 

Term

 

MAP ANNEX  I (ix)

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

 

Definition

The manufacture or upgrading of heavy water or deuteriumHeavy 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.

Term

 

MAP ANNEX  I (x)

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

 

Definition

 

 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.


 

Term

 

 

MAP ANNEX  I (xi)

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

 

 

Definition

 

 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.

 

Term

 

MAP ANNEX  I (xii)

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

 

Definition

 

 The manufacture of reactor control rods.

 

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

 

Term

 

MAP ANNEX  I (xiii)

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

 

Definition

 

 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.

 

Term

 

MAP ANNEX  I (xiv)

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

 

Definition

 

 The manufacture of irradiated fuel element chopping machines.

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

 

Term

 

 

MAP ANNEX  I (xv)

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

 

 

Definition

 

 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

 

Term

 

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)


 

Definition

 

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.

 

Term

 

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)

 

Definition

 

 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.

 

Term

 

 

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 Explanatory note)

 

 

Definition

 

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"

 

Term

 

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

 

Definition

 

 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.

 


 


 

Term

 

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

(Explanatory Note)

 

Definition

 

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.

 

Term

 

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

 

Definition

 

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.

 

Term

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

1.4   Reactor control rods

(Definition & Explanatory note)

 

 

Definition

 

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.

 

Term

 

 

ANNEX  I

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

 PROTOCOL

(List All Activities)

 

Definition

(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

 

Term

 

 

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


 

 

 

Definition

 

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).

 

Term

 

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

 

 

Definition

 

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.

 

Term

 

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

 

1.7.  Primary coolant pumps.

(Definition and Explanatory Note)

 

 

 

Definition

 

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

 

 

Term

 

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

 

 

Definition

 

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.

 

Term

 

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)

 

Definition

 

Graphite having a purity level better than 5 parts per million boron equivalent and with a density greater than 1.50 g/cmfor 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

 

 

Term

 

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)

Definition

 

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.

 


 

Term

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, 2nd Paragraph)

Definition

 

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.

 

 

Term

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, 3rd, 4th and 5th Ps)

 

 

Definition

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:

 

Term

 

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

3.1. Irradiated fuel element chopping machine

 

 

 

Definition

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.

Term

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

 

Definition

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.

Term

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.


 

 

 

Definition

 

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.

 

Term

 

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)

 

 

 

Definition

 

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.

 

Term

 

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 II: Especially designed storage vessels)

 

Definition

 

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

 

Term

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

Definition

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.

Term

 

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

 

 

 

Definition

 

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.

 

 

 

Term

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

 

 

Definition

 

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

 

Term

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)

Definition

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:

Term

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 

 

prepared for use in gas centrifuges.

 

 

Definition

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.

Term

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  

(a) Complete rotor assemblies

Definition

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.

Term

 

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

Definition

 

(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.

 

Term

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

Definition

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.

Term

 

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

 

Definition

 

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.

 

Term

 

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

 

Definition

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

Term

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)


Definition

The materials used for centrifuge rotating components are:

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

(b) Aluminium alloys capable of an ultimate tensile strength of 0.46 x 109 N/m (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 10 m or greater ('Specific Modulus' is the Young's Modulus in N/mdivided by the specific weight in N/m3; 'Specific Ultimate Tensile Strength' is the ultimate tensile strength in N/m divided by the specific weight in N/m3


Term

 

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

 

 

Definition

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(10gauss-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

Term

 

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

 

 

 

Definition

 

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.

 

Term

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

Definition

 

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.

 

Term

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

Definition

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.

Term

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

Definition

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 UF

Term

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

Definition

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

Term

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

Definition

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.

Term

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

Definition

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.

Term

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

Definition

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.

Term

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)

Definition

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

Term

 

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)

 

 

Definition

 

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.

 

Term

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)

Definition

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.

Term

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))

 

Definition

(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.

Term

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

Definition

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.

Term

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

Definition

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

Term

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

Definition

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).

Term

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

Definition

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).

Term

 

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)

 

 

 

Definition

 

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.

 

Term

 

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 2)

 

 

 

 

Definition

 

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.

 

Term

 

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)

 

 

 

Definition

 

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.

 

Term

 

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

 

Definition

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.

Term

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))

Definition

(a) Especially designed or prepared large vacuum manifolds, vacuum headers and vacuum pumps having a suction capacity of 5 m/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.

Term

 

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

 

 

Definition

 

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.

 

Term

 

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)

 

 

Definition

 

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.

 

Term

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


(Introductory Note)


 

Definition

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.

Term

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)

 

 

Definition

The items listed in this section either come into direct contact with the UFprocess 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.

Term

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

Definition

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.

Term

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)


Definition

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.

Term

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)

Definition

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 m/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.

Term

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

Definition

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.

Term

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

Definition

 

Especially designed or prepared heat exchangers made of or protected by materials resistant to corrosion by UF6.

Term

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)

Definition

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.

Term

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))

Definition

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

Term

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

Definition

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.

Term

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))

Definition

(a) Especially designed or prepared vacuum systems having a suction capacity of 5 m/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.

Term

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

Definition

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.

Term

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)

Definition

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.

Term

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)

Definition

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

Term

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 ( Intro note paragraph 1)

Definition

 

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

Term

 

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 ( Intro note paragraph 2)

 

Definition

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.

Term

 

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 ( Intro note paragraph 3).

 

Definition

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.

Term

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

5.6.1. Liquid-liquid exchange columns (Chemical exchange)

Definition

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)

Term

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  5.6.2. Liquid-liquid centrifugal contactors (Chemical exchange)

Definition

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).

Term

 

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)

 

Definition

 

(a) Especially designed or prepared electrochemical reduction cells to reduce uranium from one valence state to another for uranium enrichment using the chemical exchange process. The cell materials in contact with process solutions must be corrosion resistant to concentrated hydrochloric acid solutions.

EXPLANATORY NOTE

The cell cathodic compartment must be designed to prevent re-oxidation of uranium to its higher valence state. To keep the uranium in the  cathodic compartment, the cell may have an impervious diaphragm membrane constructed of special  cation exchange material. The cathode consists of a suitable solid conductor such as graphite.

 

 

 

Term

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.(b) Uranium reduction systems and equipment (Chemical exchange) (def +Explanatory note)

Definition

(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)

Term

 

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)

 

Definition

 

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.

 

Term

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)

Definition

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

Term

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

Definition

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

Term

 

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)

 

Definition

 

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).

 

Term

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)

Definition

(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+


Term

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)

Definition

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

Term

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)

Definition

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.

Term

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)

Definition

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.

Term

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)

Definition

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.

Term

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)

Definition

 

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.

 

Term

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)

Definition

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

Term

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)

Definition

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

Term

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)

Definition

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

Term

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)

Definition

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

Term

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)

Definition

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.

Term

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)

Definition

 

Especially designed or prepared systems for fluorinating UF5 (solid) to UF(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.

 

Term

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)

Definition

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

Term

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.

5.7.11. Feed systems/product and tails withdrawal systems (MLIS) (Def + a b c & d)

Definition

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 container

Term

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.

5.7.12. UF6/carrier gas separation systems (MLIS) (def + Explanatory note--intro sentence + a b & c)

Definition

Especially designed or prepared process systems for separating UF6 from carrier gas. The carrier gas may be nitrogen, argon, or other gas.

EXPLANATORY NOTE

These systems may incorporate equipment such as:

(a) Cryogenic heat exchangers or cryoseparators capable of temperatures of -120oC or less, or

(b) Cryogenic refrigeration units capable of temperatures of -120 oC or less, or

(c) UF6 cold traps capable of temperatures of -20o C or less

Term

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.

5.7.13. Laser systems (AVLIS, MLIS and CRISLA) (def + Explanatory Note)

Definition

Lasers or laser systems especially designed or prepared for the separation of uranium isotopes.

EXPLANATORY NOTE

The laser system for the AVLIS process usually consists of two lasers: a copper vapor laser and a dye laser. The laser system for MLIS usually consists of a CO2 or  excimer laser and a  multi-pass optical cell with revolving mirrors at both ends. Lasers or laser systems for both processes require a spectrum frequency stabilizer for operation over extended periods of time.

Term

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

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plant

(Intro Note)

Definition

In the plasma separation process, a plasma of uranium ions passes through an electric field tuned to the U-235 ion resonance frequency so that they preferentially absorb energy and increase the diameter of their corkscrewlike orbits. Ions with a large-diameter path are trapped to produce a product enriched in U-235. The plasma, which is made by ionizing uranium vapor, is contained in a vacuum chamber with a high-strength magnetic field produced by a superconducting magnet. The main technological systems of the process include the uranium plasma generation system, the separator module with  superconducting magnet and metal removal systems for the collection of 'product' and 'tails'.

Term

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

 

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plant

5.8.1. Microwave power sources and antenna


Definition

Especially designed or prepared microwave power sources and antennae for producing or accelerating ions and having the following characteristics: greater than 30 GHz frequency and greater than 50 kW mean power output

for ion production.

Term

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

 

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plant

5.8.2. Ion excitation coils

Definition

Especially designed or prepared radio frequency ion excitation coils for frequencies of more than 100 kHz and capable of handling more than 40 kW mean power.

Term

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

 

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plant

5.8.3. Uranium plasma generation systems

Definition

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

Term

 

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

 

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plants

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

 

Definition

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.

Term

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

 

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plants

5.8.5. Uranium metal 'product' and 'tails' collector assemblies

Definition

Especially designed or prepared 'product' and 'tails' collector assemblies for uranium metal in solid form. These collector assemblies are made of or protected by materials resistant to the heat and corrosion of uranium metal vapor, such as yttria-coated graphite or tantalum.

Term

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

 

5.8. Especially designed or prepared systems, equipment and components for use in plasma separation enrichment plants

5.8.6. Separator module housing (def + Explanatory Note)

Definition

Cylindrical vessels especially designed or prepared for use in plasma separation enrichment plants for containing the uranium plasma source, radio-frequency drive coil and the 'product' and 'tails' collectors.

EXPLANATORY NOTE

These housings have a multiplicity of ports for electrical feed-throughs, diffusion pump connections and instrumentation diagnostics and monitoring. They have provisions for opening and closure to allow for refurbishment of internal components and are constructed of a suitable nonmagnetic material such as stainless steel

Term

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

 

5.9. Especially designed or prepared systems, equipment and components for use in electromagnetic enrichment plants

(Introductory Note)

Definition

In the electromagnetic process, uranium metal ions produced by ionization of a salt feed material (typically UCl4) are accelerated and passed through a magnetic field that has the effect of causing the ions of different isotopes to follow different paths. The major components of an electromagnetic isotope separator include: a magnetic field for ion-beam diversion/separation of the isotopes, an ion source with its acceleration system, and a collection system for the separated ions. Auxiliary systems for the process include the magnet  power supply system, the ion source high-voltage power supply system, the vacuum system, and extensive chemical handling systems for recovery of product and cleaning/recycling of components.

Term

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

5.9. Especially designed or prepared systems, equipment and componentsfor use in electromagnetic enrichment plant

5.9.1. Electromagnetic isotope separators (Def + types (a),( b),  (c)+ Explanatory Note, (d))

Definition

Electromagnetic isotope separators especially designed or prepared for the separation of uranium isotopes, and equipment and components therefor, including: (a) Ion sources Especially designed or prepared single or multiple uranium ion sources consisting of a vapor source, ionizer, and beam accelerator, constructed of suitable materials such as graphite, stainless steel, or copper, and capable of providing a total ion beam current of 50 mA or greater. (b) Ion collectors Collector plates consisting of two or more slits and pockets especially designed or prepared for collection of enriched and depleted uranium ion beams and constructed of suitable materials such as graphite or stainless steel. (c) Vacuum housings Especially designed or prepared vacuum housings for uranium electromagnetic separators, constructed of suitable non-magnetic materials such as stainless steel and designed for operation at pressures of 0.1 Pa or lower.EXPLANATORY NOTE The housings are specially designed to contain the ion sources, collector plates and water-cooled liners and have provision for diffusion pump connections and opening and closure for removal and reinstallation of these components.  (d) Magnet pole pieces, Especially designed or prepared magnet pole pieces having a diameter greater than 2 m used to maintain a constant magnetic field within an electromagnetic isotope separator and to transfer the magnetic field between adjoining separators

Term

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

5.9.1. Electromagnetic isotope separators

(Explanatory Note)

Definition
Term

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

5.9. Especially designed or prepared systems, equipment and componentsfor use in electromagnetic enrichment plant

5.9.2. High voltage power supplies

 

Definition

Especially designed or prepared high-voltage power supplies for ion sources, having all of the following characteristics: capable of continuous operation, output voltage of 20,000 V or greater, output current of 1 A or

greater, and voltage regulation of better than 0.01% over a time period of 8 hours.

Term

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

5.9. Especially designed or prepared systems, equipment and componentsfor use in electromagnetic enrichment plants

5.9.3. Magnet power supplies

Definition

Especially designed or prepared high-power, direct current magnet power supplies having all of the following characteristics: capable of continuously producing a current output of 500 A or greater at a voltage of 100 V or

greater and with a current or voltage regulation better than 0.01% over a period of 8 hours.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

INTRODUCTORY NOTE P1 & P2

Definition

Heavy water can be produced by a variety of processes. However, the two processes that have proven to be commercially viable are the waterhydrogen  sulphide exchange process (GS process) and the ammoniahydrogen exchange process.


The GS process is based upon the exchange of hydrogen and deuterium between water and hydrogen  sulphide within a series of towers which are operated with the top section cold and the bottom section hot. Water flows down the towers while the hydrogen sulphide gas circulates from the bottom to the top of the towers. A series of perforated trays are used to promote mixing between the gas and the water. Deuterium migrates to the water at low temperatures and to the hydrogen sulphide at high temperatures. Gas or  water, enriched in deuterium, is removed from the first stage towers at the junction of the hot and cold sections and the process is repeated in subsequent stage towers. The product of the last stage, water enriched up to 30% in deuterium, is sent to a distillation unit to produce reactor grade heavy water, i.e., 99.75% deuterium oxide.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

Introductory Note P3 

 

Definition

The ammonia-hydrogen exchange process can extract deuterium from synthesis gas through contact with liquid ammonia in the presence of a catalyst. The synthesis gas is fed into exchange towers and to an ammonia converter. Inside the towers the gas flows from the bottom to the top while the liquid ammonia flows from the top to the bottom. The deuterium is stripped from the hydrogen in the synthesis gas and concentrated in the ammonia. The ammonia then flows into an ammonia cracker at the bottom of the tower while the gas flows into an ammonia converter at the top. Further enrichment takes place in subsequent stages and reactor grade heavy water is produced through final distillation. The synthesis gas feed can be provided by an ammonia plant that, in turn, can be constructed in association with a heavy water ammonia-hydrogen exchange plant. The ammonia-hydrogen exchange process can also use ordinary water as a feed source of deuterium.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

Introductory Note P4

Definition

Many of the key equipment items for heavy water production plants using GS or the ammonia-hydrogen exchange processes are common to several segments of the chemical and petroleum industries. This is particularly so for small plants using the GS process. However, few of the items are available "off-the-shelf". The GS and ammonia-hydrogen processes require the handling of large quantities of flammable, corrosive and toxic fluids at elevated pressures. Accordingly, in establishing the design and operating standards for plants and equipment using these processes, careful attention to the materials selection and specifications is required to ensure long service life with high safety and reliability factors. The choice of scale is primarily a function of economics and need. Thus, most of the equipment

items would be prepared according to the requirements of the customer.

Term

 

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

Introductory Note P5 & P6

 

Definition

Finally, it should be noted that, in both the GS and the ammonia-hydrogen exchange processes, items of equipment which individually are not especially designed or prepared for heavy water production can be assembled into systems which are especially designed or prepared for producing heavy water. The catalyst production system used in the ammonia-hydrogen exchange process and water distillation systems used for the final concentration of heavy water to reactor-grade in either process are examples of such systems. The items of equipment which are especially designed or prepared for the production of heavy water utilizing either the water-hydrogen  sulphide exchange process or the ammonia-hydrogen exchange process include the following:

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

6.1. Water - Hydrogen Sulphide Exchange Tower

Definition

Exchange towers fabricated from fine carbon steel (such as ASTM A516)

with diameters of 6 m (20 ft) to 9 m (30 ft), capable of operating at

pressures greater than or equal to 2  MPa (300  psi) and with a corrosion allowance of 6 mm or greater, especially designed or prepared for heavy water production utilizing the water-hydrogen sulphide exchange process.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

6.2. Blowers and Compressors

Definition

Single stage, low head (i.e., 0.2  MPa or 30  psi) centrifugal blowers or compressors for hydrogen-sulphide gas circulation (i.e., gas containing more than 70% H2S) especially designed or prepared for heavy water production utilizing the water-hydrogen  sulphide exchange process. These blowers or compressors have a throughput capacity greater than or equal to 56 m3/second (120,000 SCFM) while operating at pressures greater than or equal to 1.8  MPa (260  psi) suction and have seals designed for wet H2S service.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

6.3. Ammonia-Hydrogen Exchange Towers

Definition

Ammonia-hydrogen exchange towers greater than or equal to 35 m (114.3 ft) in height with diameters of 1.5 m (4.9 ft) to 2.5 m (8.2 ft) capable of operating at pressures greater than 15 MPa (2225 psi) especially designed or prepared for heavy water production utilizing the ammonia-hydrogen exchange process. These towers also have at least one flanged axial opening of the same diameter as the cylindrical part through which the tower internals can be inserted or withdrawn.

Term

 

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

6.4. Tower Internals and Stage Pumps

 

 

Definition

 

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

 

Term

 

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

6.5. Ammonia Cracker

 

Definition

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

Term

 

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

 

6.6. Infrared Absorption Analyzers

 

 

Definition

 

Infrared absorption analyzers capable of "on-line" hydrogen/deuterium ratio analysis where deuterium concentrations are equal to or greater than 90%

 

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

6. Plants for the production of heavy water, deuterium and deuterium compounds and equipment especially designed or prepared therefor

6.7. Catalytic Burners

Definition

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

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especially designed or prepared therefor

Introductory Note

Definition

Uranium conversion plants and systems may perform one or more transformations from one uranium chemical species to another, including: conversion of uranium ore concentrates to UO3, conversion of UO3 to UO2conversion of uranium oxides to UF4 or UF6, conversion of UF4 to UF6conversion of UF6 to UF4, conversion of UF4 to uranium metal, and conversion of uranium fluorides to UO2. Many of the key equipment items for uranium conversion plants are common to several segments of the chemical process industry. For example, the types of equipment employed in these processes may include: furnaces, rotary kilns,  fluidized bed reactors, flame tower reactors, liquid centrifuges, distillation columns and liquidliquid extraction columns. However, few of the items are available "off-theshelf"; most would be prepared according to the requirements and  specifications of the customer. In some instances, special design and construction considerations are required to address the corrosive properties of some of the chemicals handled (HF, F2, ClF3, and uranium fluorides).

Finally, it should be noted that, in all of the uranium conversion processes, items of equipment which individually are not especially designed or prepared for uranium conversion can be assembled into systems which are especially designed or prepared for use in uranium conversion.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

 

7. Plants for the conversion of uranium and equipment especially designed or prepared therefor

7.1. Especially designed or prepared systems for the conversion of uranium ore concentrates to UO3

Explanatory Note

 

Definition

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

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 


7. Plants for the conversion of uranium and equipment especially designed or prepared therefor

7.2. Especially designed or prepared systems for the conversion of UO3 to UF

Explanatory Note

Definition

Conversion of UO3 to UF6 can be performed directly by  fluorination. The process requires a source of fluorine gas or chlorine trifluoride.

Term

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LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especially designed or prepared therefor

7.3. Especially designed or prepared systems for the conversion of UO3 to UO2

Explanatory Note

Definition

Conversion of UO3 to UO2 can be performed through reduction of UO3 with cracked ammonia gas or hydrogen.

Term

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LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especially designed or prepared therefor

7.4. Especially designed or prepared systems for the conversion of UO2 to UF4

Explanatory Note

Definition

Conversion of UO2 to UF4 can be performed by reacting UO2 with hydrogen fluoride gas (HF) at 300-500 o C

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especially designed or prepared therefor

7.5. Especially designed or prepared systems

for the conversion of UF4 to UF6

EXPLANATORY NOTE

Definition

Conversion of UF4 to UF6 is performed by exothermic reaction with fluorine in a tower reactor. UF6 is condensed from the hot effluent gases by passing the effluent stream through a cold trap cooled to -10 o C. The process

requires a source of fluorine gas.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especiallydesigned or prepared therefor

7.6. Especially designed or prepared systems for the conversion of UF4 to U metal

Explanatory Note

Definition

Conversion of UF4 to U metal is performed by reduction with magnesium (large batches) or calcium (small batches). The reaction is carried out at temperatures above the melting point of uranium (1130 oC).

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especiallydesigned or prepared therefor

 

7.7. Especially designed or prepared systems for the


conversion of UF6 to 

UO2


Explanatory Note

 

 

Definition

Conversion of UF6 to UO2 can be performed by one of three processes. In the first, UF6 is reduced and hydrolyzed to UO2 using hydrogen and steam. In the second, UF6 is hydrolyzed by solution in water, ammonia is added to precipitate ammonium diuranate, and the diuranate is reduced to UO2 with hydrogen at 820 o C.  In the third process, gaseous UF6, CO2, and NH3 are combined in water, precipitating ammonium  uranyl carbonate. The ammonium uranyl carbonate is combined with steam and hydrogen at 500- 600 o C to yield UO2. UF6 to UO2 conversion is often performed as the first stage of a fuel fabrication plant.

Term

ANNEX  II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL

FOR THE REPORTING OF EXPORTS AND IMPORTS

ACCORDING TO ARTICLE 2.a.(ix)

 

7. Plants for the conversion of uranium and equipment especiallydesigned or prepared therefor

7.8. Especially designed or prepared systems for the conversion of UF6 to UF4

Explanatory Note

Definition

Conversion of UF6 to UF4 is performed by reduction with hydrogen.

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