Treaty on the Non-proliferation of Nuclear Weapons

L.N. 237 of 2005

NATIONAL INTEREST (ENABLING POWERS) ACT

(CAP. 365)

Treaty on the Non-proliferation of Nuclear Weapons

(Application of Safeguards) Regulations, 2005

IN exercise of the powers conferred by article 3 of the National

Interest (Enabling Powers) Act, the Prime Minister has made the

following regulations>-

The title of these regulations is the Treaty on the Non-

proliferation of Nuclear Weapons (Application of Safeguards)

Regulations, 2005.

In these regulations, unless the context otherwise requires -

“Agency” means the International Atomic Energy Agency<

“the Protocol” means the Protocol Additional to the

Agreement between Malta and the International Atomic Energy

Agency for the Application of Safeguards in connection with the

Treaty on the Non-proliferation of Nuclear Weapons, including

annexes attached thereto, as set out in Schedule I to these

regulations.

“Radiation Protection Board” means the Radiation Protection

Board established by virtue of regulation 9 of the Nuclear Safety

and Radiation Protection Regulations, 2003.

(1) The Radiation Protection Board shall be the competent

authority responsible for the implementation of the obligations arising

out of the Protocol, and it has all such powers as are necessary to fulfill

such obligations.

(2) The Radiation Protection Board shall have the right to

nominate any representative or representatives to accompany any

Agency Inspector during any visit to any site or location as specified in

the Protocol.

Any Inspector designated by the Agency shall have access to

any site or location as specified in Articles 5 to 9 of the Protocol, and

under such terms and conditions as specified in Article 4 of the Protocol.

No person shall refuse access to any Agency Inspector or in Refusal

Agency Inspectors.

any other way threaten, molest or disturb Agency Inspectors and any

Radiation Protection Board representative or representatives in the

performance of their duties.

No person shall, in connection with any matter under these Obligation to

furnish correct

regulations-

information.

(a) furnish any information which that person knows to be

false in a material particular, or recklessly furnishes any information

which is false in a material particular< or

(b) with intent to deceive, produce, furnish, send or

otherwise make use of any document which is false in a material

particular< or

(c) wilfully refuse or without lawful excuse, the proof

whereof shall lie on that person, withhold any material information<

or

(d) knowingly or recklessly make any incorrect statement

or entry in any record or return or on any document furnished

under these regulations< or

(e) unlawfully refuse or fail to answer to the best of that

personís knowledge any question made to him or her by an Agency

Inspector or a Radiation Protection Board representative in the

exercise of their functions< or

(f) unlawfully refuse or fail to comply with any requirement

duly provided under these regulations.

The Schedule to these regulations, including the Annexes Schedule to have

force of law.

thereto, shall have the force of law in Malta.

(1) Any person who acts in contravention of the provisions Offences and

penalties.

of regulations 6 and 7, and any person who conspires or attempts, or

aids, abets, counsels or procures any other person, to contravene the

regulations aforementioned, shall be guilty of an offence.

(2) Any person who commits an offence against these

regulations shall, on conviction, be liable to imprisonment for a period

of not more than two years or to a fine (multa) of not less than two

hundred liri but not exceeding five thousand liri, or to both such fine

and imprisonment.

The Court of Magistrates (Malta) and the Court of Magistrates

(Gozo) as courts of criminal judicature, shall, notwithstanding the

provisions of article 370 of the Criminal Code, be competent to try all

offences against these regulations.

Where the facts constituting a breach of any of the above

provisions also constitute a breach of any other law prohibited by the

particular regulations, proceedings shall not be taken in respect of the

breach of the regulations hereabove, but only in respect of the breach of

the other law.

The text of the Protocol is being published in the English

language in the Schedule to these regulations.

PROTOCOL ADDITIONAL TO THE AGREEMENT BETWEEN THE REPUBLIC OF

MALTA AND THE INTERNATIONAL ATOMIC ENERGY AGENCY FOR THE

APPLICATION OF SAFEGUARDS IN CONNECTION WITH THE TREATY ON THE

NON-PROLIFERATION OF NUCLEAR WEAPONS

WHEREAS the Republic of Malta (hereinafter referred to as "Malta") and the

International Atomic Energy Agency (hereinafter referred to as the "Agency") are parties to an

Agreement for the Application of Safeguards in Connection with the Treaty on the Non-

Proliferation of Nuclear Weapons (hereinafter referred to as the "Safeguards Agreement"), which

entered into force on 13 November 1990;

AWARE OF the desire of the international community to further enhance nuclear non-

proliferation by strengthening the effectiveness and improving the efficiency of the Agency's

safeguards system;

RECALLING that the Agency must take into account in the implementation of

safeguards the need to: avoid hampering the economic and technological development of Malta

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 Malta and the Agency have agreed as follows

RELATIONSHIP BETWEEN THE PROTOCOL AND THE SAFEGUARDS

AGREEMENT

Article 1

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.

PROVISION OF INFORMATION

Article 2

Malta shall provide the Agency with a declaration containing

(i)

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, Malta.

(ii)

Information identified by the Agency on the basis of expected gains in

effectiveness or efficiency, and agreed to by Malta, on operational activities of

safeguards relevance at facilities and locations outside facilities where nuclear

material is customarily used.

(iii)

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.

(iv)

A description of the scale of operations for each location engaged in the activities

specified in Annex I to this Protocol.

(v)

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 Malta as a whole. Malta 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.

(vi)

Information regarding source material which has not reached the composition and

purity suitable for fuel fabrication or for being isotopically enriched, as follows

(a)

The quantities, the chemical composition, the use or intended use of such

material, whether in nuclear or non-nuclear use, for each location in Malta 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 Malta 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;

(b)

The quantities, the chemical composition and the destination of each

export out of Malta, of such material for specifically non-nuclear purposes

in quantities exceeding

(1)

Ten metric tons of uranium, or for successive exports of uranium

from Malta 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 Malta to the same State, each of less than twenty metric

tons, but exceeding a total of twenty metric tons for the year;

(c)

The quantities, chemical composition, current location and use or intended

use of each import into Malta of such material for specifically non-nuclear

purposes in quantities exceeding

(1)

Ten metric tons of uranium, or for successive imports of uranium

into Malta 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 Malta 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.

(vii)

(a)

Information regarding the quantities, uses and locations of nuclear

material exempted from safeguards pursuant to Article 36 of the Safeguards

Agreement;

(b)

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 Article 35(b) of the safeguards Agreement but not yet in a

non-nuclear end-use form, in quantities exceeding those set out in Article 36 of

the Safeguards Agreement. The provision of this information does not require

detailed nuclear material accountancy.

(viii) 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 Article 11 of the Safeguards

Agreement. 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.

(ix)

The following information regarding specified equipment and non-nuclear

material listed in Annex II

(a)

For each export out of Malta of such equipment and material: the identity,

quantity, location of intended use in the receiving State and date or, as

appropriate, expected date, of export;

(b)

Upon specific request by the Agency, confirmation by Malta, as importing

State, of information provided to the Agency in accordance with

paragraph (a) above.

(x)

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 Malta.

Malta shall make every reasonable effort to provide the Agency with the following

information

(i)

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 Malta but

which are not funded, specifically authorized or controlled by, or carried out on

behalf of, Malta. For the purpose of this paragraph, "processing" of intermediate

or high-level waste does not include repackaging of the waste or its conditioning

not involving the separation of elements, for storage or disposal.

(ii)

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.

Upon request by the Agency, Malta shall provide amplifications or clarifications of

any information it has provided under this Article, in so far as relevant for the purpose

of safeguards.

Article 3

Malta 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.

Malta 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, Malta shall so indicate.

Malta 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.

Malta 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.

Malta 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.

Malta and the Agency shall agree on the timing and frequency of the provision of the

information identified in Article 2.a.(ii).

Malta shall provide to the Agency the information in Article 2.a.(ix)(b) within sixty days

of the Agency's request.

COMPLEMENTARY ACCESS

Article 4

The following shall apply in connection with the implementation of complementary

access under Article 5 of this Protocol

The Agency shall not mechanistically or systematically seek to verify the information

referred to in Article 2; however, the Agency shall have access to

(i)

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;

(ii)

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;

(iii)

Any location referred to in Article 5.a.(iii) to the extent necessary for the Agency

to confirm, for safeguards purposes, Malta's declaration of the decommissioned

status of a facility or location outside facilities where nuclear material was

customarily used.

(i)

except as provided in paragraph (ii) below, the Agency shall give Malta 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.

Advance notice shall be in writing and shall specify the reasons for access and the

activities to be carried out during such access.

In the case of a question or inconsistency, the Agency shall provide Malta 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 Malta has been provided with such an opportunity.

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

hours.

Malta shall have the right to have Agency inspectors accompanied during their access by

representatives of Malta, provided that the inspectors shall not thereby be delayed or

otherwise impeded in the exercise of their functions.

Article 5

Malta shall provide the Agency with access to

(i)

Any place on a site;

(ii)

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

(iii)

Any decommissioned facility or decommissioned location outside facilities where

nuclear material was customarily used.

Any location identified by Malta 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 Malta

is unable to provide such access, Malta shall make every reasonable effort to satisfy

Agency requirements, without delay, through other means.

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

Malta is unable to provide such access, Malta shall make every reasonable effort to

satisfy Agency requirements, without delay, at adjacent locations or through other means.

Article 6

When implementing Article 5, the Agency may carry out the following activities

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 Malta.

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

Malta.

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

Malta.

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 Malta and the Agency,

other objective measures.

Article 7

Upon request by Malta, the Agency and Malta 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.

Malta may, when providing the information referred to in Article 2, inform the Agency of

he places at a site or location at which managed access may be applicable.

Pending the entry into force of any necessary Subsidiary Arrangements, Malta may have

recourse to managed access consistent with the provisions of paragraph a. above.

Article 8

Nothing in this Protocol shall preclude Malta 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.

Article 9

Malta shall provide the Agency with access to locations specified by the Agency to carry

out wide-area environmental sampling, provided that if Malta 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 therefore have been approved by the Board and following consultations

between the Agency and Malta

Article 10

The Agency shall inform Malta of

The activities carried out under this Protocol, including those in respect of any questions

or inconsistencies the Agency had brought to the attention of Malta, within sixty days of

the activities being carried out by the Agency.

The results of activities in respect of any questions or inconsistencies the Agency had

brought to the attention of Malta, as soon as possible but in any case within thirty days

of the results being established by the Agency.

The conclusions it has drawn from its activities under this Protocol. The conclusions

shall be provided annually.

DESIGNATION OF AGENCY INSPECTORS

Article 11

(i)

The Director General shall notify Malta of the Board's approval of any

Agency official as a safeguards inspector. Unless Malta advises the Director

General of its ejection of such an official as an inspector for Malta within three

months of receipt of notification of the Board's approval, the inspector so notified

to Malta shall be considered designated to Malta.

(ii)

The Director General, acting in response to a request by Malta or on his own

initiative, shall immediately inform Malta of the withdrawal of the designation of

any official as an inspector for Malta.

A notification referred to in paragraph a. above shall be deemed to be received by Malta

seven days after the date of the transmission by registered mail of the notification by the

Agency to Malta.

VISAS

Article 12

Malta 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 Malta 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 Malta.

SUBSIDIARY ARRANGEMENTS

Article 13

Where Malta or the Agency indicates that it is necessary to specify in Subsidiary

Arrangements how measures laid down in this Protocol are to be applied, Malta 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.

Pending the entry into force of any necessary Subsidiary Arrangements, the Agency shall

be entitled to apply the measures laid down in this Protocol.

COMMUNICATIONS SYSTEMS

Article 14

Malta shall permit and protect free communications by the Agency for official purposes between

Agency inspectors in Malta 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 Malta, the

right to make use of internationally established systems of direct communications, including

satellite systems and other forms of telecommunication, not in use in Malta. At the request of

Malta 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.

Communication and transmission of information as provided for in paragraph a. above

hall take due account of the need to protect proprietary or commercially sensitive

information or design information which Malta regards as being of particular sensitivity.

PROTECTION OF CONFIDENTIAL INFORMATION

Article 15

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.

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;

(iii)

Procedures in cases of breaches or alleged breaches of confidentiality.

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

by the Board.

ANNEXES

Article 16

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.

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.

ENTRY INTO FORCE

Article 17

This Protocol shall enter into force on the date on which the Agency receives from Malta

written notification that Malta's statutory and/or constitutional requirements for entry into

force have been met.

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

Protocol provisionally.

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.

DEFINITIONS

Article 18

For the purpose of this Protocol

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.

Site means that area delimited by Malta 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 items identified by Malta under Article 2.a.(iv) above.

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.

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.

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

uranium-235.

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.

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.

.

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 Malta.

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.

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.

ANNEX I

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

(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.

(ii)

The manufacture of diffusion barriers.

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

(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.

(iv)

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.

(v)

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.

(vi)

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.

(vii)

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.

(viii) The manufacture of zirconium tubes.

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

(ix)

The manufacture or upgrading of heavy water or deuterium.

Heavy water or deuterium means deuterium, heavy water (deuterium oxide) and any

other deuterium compound in which the ratio of deuterium to hydrogen atoms exceeds

1:5000.

(x)

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/cm 3 .

(xi)

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.

(xii)

The manufacture of reactor control rods.

Reactor control rods means rods as described in entry 1.4 of Annex II.

(xiii) 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.

(xiv)

The manufacture of irradiated fuel element chopping machines.

Irradiated fuel element chopping machines means equipment as described in entry 3.1

of Annex II.

(xv)

The construction of hot cells.

Hot cells means a cell or interconnected cells totalling at least 6 m 3 in volume with

shielding equal to or greater than the equivalent of 0.5 m of concrete, with a density of

3.2 g/cm 3 or greater, outfitted with equipment for remote operations.

ANNEX II

LIST OF SPECIFIED EQUIPMENT AND NON-NUCLEAR MATERIAL FOR THE

REPORTING OF EXPORTS AND IMPORTS ACCORDING TO ARTICLE 2.a.(ix)

1. Reactors and equipment therefor

Complete nuclear reactors

Nuclear reactors capable of operation so as to maintain a controlled self-sustaining fission

chain reaction, excluding zero energy reactors, the latter being defined as reactors with a

designed maximum rate of production of plutonium not exceeding 100 grams per year.

EXPLANATORY NOTE

A "nuclear reactor" basically includes the items within or attached directly to the reactor

vessel, the equipment which controls the level of power in the core, and the components

which normally contain or come in direct contact with or control the primary coolant of

the reactor core.

It is not intended to exclude reactors which could reasonably be capable of modification

to produce significantly more than 100 grams of plutonium per year. Reactors designed

for sustained operation at significant power levels, regardless of their capacity for

plutonium production, are not considered as "zero energy reactors".

Reactor pressure vessels

Metal vessels, as complete units or as major shop-fabricated parts therefor, which are

especially designed or prepared to contain the core of a nuclear reactor as defined in

paragraph 1.1. above and are capable of withstanding the operating pressure of the

primary coolant.

EXPLANATORY NOTE

A top plate for a reactor pressure vessel is covered by item 1.2. as a major shop-

fabricated part of a pressure vessel.

Reactor internals (e.g. support columns and plates for the core and other vessel internals,

control rod guide tubes, thermal shields, baffles, core grid plates, diffuser plates, etc.) are

normally supplied by the reactor supplier. In some cases, certain internal support

components are included in the fabrication of the pressure vessel. These items are

sufficiently critical to the safety and reliability of the operation of the reactor (and,

therefore, to the guarantees and liability of the reactor supplier), so that their supply,

outside the basic supply arrangement for the reactor itself, would not be common

practice. Therefore, although the separate supply of these unique, especially designed and

prepared, critical, large and expensive items would not necessarily be considered as

falling outside the area of concern, such a mode of supply is considered unlikely.

Reactor fuel charging and discharging machines

Manipulative equipment especially designed or prepared for inserting or removing fuel in

a nuclear reactor as defined in paragraph 1.1. above 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.

Reactor control rods

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.

Reactor pressure tubes

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).

Zirconium tubes

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.

Primary coolant pumps

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.

2. Non-nuclear materials for reactors

Deuterium and heavy water

Deuterium, heavy water (deuterium oxide) and any other deuterium compound in which

the ratio of deuterium to hydrogen atoms exceeds 1:5000 for use in a nuclear reactor as

defined in paragraph 1.1. above in quantities exceeding 200 kg of deuterium atoms for

any one recipient country in any period of 12 months.

Nuclear grade graphite

Graphite having a purity level better than 5 parts per million boron equivalent and with a

density greater than 1.50 g/cm 3 for use in a nuclear reactor as defined in paragraph1.1.

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.

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

designed or prepared therefor

INTRODUCTORY NOTE

Reprocessing irradiated nuclear fuel separates plutonium and uranium from intensely

radioactive fission products and other transuranic elements. Different technical processes

can accomplish this separation. However, over the years Purex has become the most

commonly used and accepted process. Purex involves the dissolution of irradiated nuclear

fuel in nitric acid, followed by separation of the uranium, plutonium, and fission products

by solvent extraction using a mixture of tributyl phosphate in an organic diluent.

Purex facilities have process functions similar to each other, including: irradiated fuel

element chopping, fuel dissolution, solvent extraction, and process liquor storage. There

may also be equipment for thermal denitration of uranium nitrate, conversion of

plutonium nitrate to oxide or metal, and treatment of fission product waste liquor to a

form suitable for long term storage or disposal. However, the specific type and

configuration of the equipment performing these functions may differ between Purex

facilities for several reasons, including the type and quantity of irradiated nuclear fuel to

be reprocessed and the intended disposition of the recovered materials, and the safety and

maintenance philosophy incorporated into the design of the facility.

A "plant for the reprocessing of irradiated fuel elements" includes the equipment and

components which normally come in direct contact with and directly control their

radiated 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

Irradiated fuel element chopping machines

INTRODUCTORY NOTE

This equipment breaches the cladding of the fuel to expose the irradiated nuclear material

to dissolution. Especially designed metal cutting shears are the most commonly

employed, although advanced equipment, such as lasers, may be used. 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.

Dissolvers

INTRODUCTORY NOTE

Dissolvers normally receive the chopped-up spent fuel. In these critically safe vessels, the

irradiated nuclear material is dissolved in nitric acid and the remaining hulls removed

from the process stream.

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.

Solvent extractors and solvent extraction equipment

INTRODUCTORY NOTE

Solvent extractors both receive the solution of irradiated fuel from the dissolvers and the

organic solution which separates the uranium, plutonium, and fission products. Solvent

extraction equipment is normally designed to meet strict operating parameters, such as

long operating lifetimes with no maintenance requirements or adaptability to easy

replacement, simplicity of operation and control, and flexibility for variations in process

conditions.

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.

Chemical holding or storage vessels

INTRODUCTORY NOTE

Three main process liquor streams result from the solvent extraction step. Holding or

storage vessels are used in the further processing of all three streams, as follows

(a)

The pure uranium nitrate solution is concentrated by evaporation and passed to a

denitration process where it is converted to uranium oxide. This oxide is re-used in the

nuclear fuel cycle.

(b)

The intensely radioactive fission products solution is normally concentrated by

evaporation and stored as a liquor concentrate. This concentrate may be subsequently

evaporated and converted to a form suitable for storage or disposal.

(c)

The pure plutonium nitrate solution is concentrated and stored pending its transfer to

further process steps. In particular, holding or storage vessels for plutonium solutions are

designed to avoid criticality problems resulting from changes in concentration and form

of this stream.

Especially designed or prepared holding or storage vessels for use in a plant for the

reprocessing of irradiated fuel. The holding or storage vessels must be resistant to the

corrosive effect of nitric acid. The holding or storage vessels are normally fabricated of

materials such as low carbon stainless steels, titanium or zirconium, or other high quality

materials. Holding or storage vessels may be designed for remote operation and

maintenance and may have the following features for control of nuclear criticality

(1)

walls or internal structures with a boron equivalent of at least two per cent, or

(2)

a maximum diameter of 175 mm (7 in) for cylindrical vessels, or

(3)

a maximum width of 75 mm (3 in) for either a slab or annular vessel.

Plutonium nitrate to oxide conversion system

INTRODUCTORY NOTE

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.

Plutonium oxide to metal production system

INTRODUCTORY NOTE

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, product

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.

4. Plants for the fabrication of fuel elements

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.

5. Plants for the separation of isotopes of uranium and equipment, other than

analytical instruments, especially designed or prepared therefor

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

Gas centrifuges and assemblies and components especially designed or prepared for

use in gas centrifuges

INTRODUCTORY NOTE

The gas centrifuge normally consists of a thin-walled cylinder(s) of between 75 mm (3in)

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 UF 6 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.

5.1.1. Rotating components

(a)

Complete rotor assemblies

Thin-walled cylinders, or a number of interconnected thin-walled cylinders,

Manufactured from one or more of the high strength to density ratio materials described

in the EXPLANATORY NOTE to this Section. If interconnected, the cylinders are joined

together by flexible bellows or rings as described in section 5.1.1.(c) following. The rotor

is fitted with an internal baffle(s) and end caps, as described in section 5.1.1.(d) and (e)

following, if in final form. However the complete assembly may be delivered only partly

assembled.

(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.

(c)

Rings or Bellows

Components especially designed or prepared to give localized support to the rotor tube or

to join together a number of rotor tubes. The bellows is a short cylinder of wall thickness

3 mm (0.12 in) or less, a diameter of between 75 mm (3 in) and 400 mm (16in), having a

convolute, and manufactured from one of the high strength to density ratio materials

described in the EXPLANATORY NOTE to this Section.

(d)

Baffles

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

especially designed or prepared to be mounted inside the centrifuge rotor tube, in order to

isolate the take-off chamber from the main separation chamber and, in some cases, to

assist the UF 6 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.

(e)

Top caps/Bottom caps

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

especially designed or prepared to fit to the ends of the rotor tube, and so contain the UF 6

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.

EXPLANATORY NOTE

The materials used for centrifuge rotating components are

(a)

Maraging steel capable of an ultimate tensile strength of 2.05 x 10 9 N/m 2 (300,000

psi) or more;

(b)

Aluminium alloys capable of an ultimate tensile strength of 0.46 x 10 9 N/m 2

(67,000 psi) or more;

(c)

Filamentary materials suitable for use in composite structures and having a

specific modulus of 12.3 x 10 6 m or greater and a specific ultimate tensile strength

of 0.3 x 10 6 m or greater ('Specific Modulus' is the Young's Modulus in N/m 2

divided by the specific weight in N/m 3 ; 'Specific Ultimate Tensile Strength' is the

ultimate tensile strength in N/m 2 divided by the specific weight in N/m 3 ).

5.1.2. Static components

(a)

Magnetic suspension bearings

Especially designed or prepared bearing assemblies consisting of an annular magnet

suspended within a housing containing a damping medium. The housing will be

manufactured from a UF 6 -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/m 3 (10 7 gauss-oersteds). In

addition to the usual material properties, it is a prerequisite that the deviation of the

magnetic axes from the geometrical axes is limited to very small tolerances (lower than

0.1 mm or 0.004 in) or that homogeneity of the material of the magnet is specially called

for.

(b)

Bearings/Dampers

Especially designed or prepared bearings comprising a pivot/cup assembly mounted on a

damper. The pivot is normally a hardened steel shaft with a hemisphere at one end with a

means of attachment to the bottom cap described in section 5.1.1.(e) at the other. The

shaft may however have a hydrodynamic bearing attached. The cup is pellet-shaped with

a hemispherical indentation in one surface. These components are often supplied

separately to the damper.

(c)

Molecular pumps

Especially designed or prepared cylinders having internally machined or extruded helical

grooves and internally machined bores. Typical dimensions are as follows: 75 mm (3 in)

to 400 mm (16 in) internal diameter, 10 mm (0.4 in) or more wall thickness, with the

length equal to or greater than the diameter. The grooves are typically rectangular in

cross-section and 2 mm (0.08 in) or more in depth.

(d)

Motor stators

Especially designed or prepared ring-shaped stators for high speed multiphase AC

hysteresis (or reluctance) motors for synchronous operation within a vacuum in the

frequency range of 600 - 2000 Hz and a power range of 50 - 1000 VA. The stators consist

of multi-phase windings on a laminated low loss iron core comprised of thin layers

typically 2.0 mm (0.08 in) thick or less.

(e)

Centrifuge housing/recipients

Components especially designed or prepared to contain the rotor tube assembly of a gas

centrifuge. The housing consists of a rigid cylinder of wall thickness up to 30 mm (1.2 in)

with precision machined ends to locate the bearings and with one or more flanges for

mounting. The machined ends are parallel to each other and perpendicular to the

cylinder's longitudinal axis to within 0.05 degrees or less. The housing may also be a

honeycomb type structure to accommodate several rotor tubes. The housings are made of

or protected by materials resistant to corrosion by UF 6 .

(f) Scoops

Especially designed or prepared tubes of up to 12 mm (0.5 in) internal diameter for the

extraction of UF 6 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 UF 6 .

Especially designed or prepared auxiliary systems, equipment and components for

gas centrifuge enrichment plants

INTRODUCTORY NOTE

The auxiliary systems, equipment and components for a gas centrifuge enrichment plant

are the systems of plant needed to feed UF 6 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' UF 6 from the centrifuges, together with

the equipment required to drive the centrifuges or to control the plant.

Normally UF 6 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' UF 6 gaseous streams flowing from the centrifuges are also passed by way of

cascade header pipework to cold traps (operating at about 203 K (-70 o C)) where they are

condensed prior to onward transfer into suitable containers for transportation orstorage.

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.

5.2.1. Feed systems/product and tails withdrawal systems

Especially designed or prepared process systems including

Feed autoclaves (or stations), used for passing UF 6 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 UF 6 from the cascades at up to 3 kPa

(0.5 psi) pressure. The desublimers are capable of being chilled to 203 K (-70 o C)

and heated to 343 K (70 o C);

'Product' and 'Tails' stations used for trapping UF 6 into containers.

This plant, equipment and pipework is wholly made of or lined with UF 6 -resistant

materials (see EXPLANATORY NOTE to this section) and is fabricated to very high

vacuum and cleanliness standards.

5.2.2. Machine header piping systems

Especially designed or prepared piping systems and header systems for handling UF 6

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 UF 6 -resistant materials (see

EXPLANATORY NOTE to this section) and is fabricated to very high vacuum and

cleanliness standards.

5.2.3. UF 6 mass spectrometers/ion sources

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of

taking 'on-line' samples of feed, product or tails, from UF 6 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.

Frequency changers

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 UF 6 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 UF 6 include stainless steel, aluminium, aluminium

alloys, nickel or alloys containing 60% or more nickel.

Especially designed or prepared assemblies and components for use in gaseous

diffusion enrichment

INTRODUCTORY NOTE

In the gaseous diffusion method of uranium isotope separation, the main technological

assembly is a special porous gaseous diffusion barrier, heat exchanger for cooling the gas

(which is heated by the process of compression), seal valves and control valves, and

pipelines. Inasmuch as gaseous diffusion technology uses uranium hexafluoride (UF 6 ), all

equipment, pipeline and instrumentation surfaces (that come in contact with the gas) must

be made of materials that remain stable in contact with UF 6 . A gaseous diffusion facility

requires a number of these assemblies, so that quantities can provide an important

indication of end use.

5.3.1. Gaseous diffusion barriers

(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 UF 6 , 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 UF 6 -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 gaseous diffusion barriers.

5.3.2. Diffuser housings

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 UF 6 -resistant materials and designed for horizontal or

vertical installation.

5.3.3. Compressors and gas blowers

Especially designed or prepared axial, centrifugal, or positive displacement compressors,

or gas blowers with a suction volume capacity of 1 m 3 /min or more of UF 6 , and with a

discharge pressure of up to several hundred kPa (100 psi), designed for long-term

operation in the UF 6 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 UF 6 .

5.3.4. Rotary shaft seals

Especially designed or prepared vacuum seals, with seal feed and seal exhaust

connections, for sealing the shaft connecting the compressor or the gas blower rotor with

the driver motor so as to ensure a reliable seal against in-leaking of air into the inner

chamber of the compressor or gas blower which is filled with UF 6 . Such seals are

normally designed for a buffer gas in-leakage rate of less than 1000 cm 3 /min (60

in 3 /min).

5.3.5. Heat exchangers for cooling UF 6

Especially designed or prepared heat exchangers made of or lined with UF 6 -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).

Especially designed or prepared auxiliary systems, equipment and components

for use in gaseous diffusion enrichment

INTRODUCTORY NOTE

The auxiliary systems, equipment and components for gaseous diffusion enrichment

plants are the systems of plant needed to feed UF 6 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' UF 6 from the

diffusion cascades. Because of the high inertial properties of diffusion cascades, any

interruption in their operation, and especially their shut-down, leads to serious

consequences. Therefore, a strict and constant maintenance of vacuum in all

technological systems, automatic protection from accidents, and precise automated

regulation of the gas flow is of importance in a gaseous diffusion plant. All this leads to a

need to equip the plant with a large number of special measuring, regulating and

controlling systems.

Normally UF 6 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' UF 6 gaseous streams flowing from exit points are passed by way of cascade header

pipework to either cold traps or to compression stations where the UF 6 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.

5.4.1. Feed systems/product and tails withdrawal systems

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 UF 6 to the gaseous diffusion

cascades;

Desublimers (or cold traps) used to remove UF 6 from diffusion cascades; Liquefaction

stations where UF 6 gas from the cascade is compressed and cooled to form liquid UF 6 ;

'Product' or 'tails' stations used for transferring UF 6 into containers.

5.4.2. Header piping systems

Especially designed or prepared piping systems and header systems for handling UF 6

within the gaseous diffusion cascades. This piping network is normally of the "double"

header system with each cell connected to each of the headers.

5.4.3. Vacuum systems

(a)

Especially designed or prepared large vacuum manifolds, vacuum headers and

vacuum pumps having a suction capacity of 5 m 3 /min (175 ft 3 /min) or more.

(b)

Vacuum pumps especially designed for service in UF 6 -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.

5.4.4. Special shut-off and control valves

Especially designed or prepared manual or automated shut-off and control bellows valves

made of UF 6 -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.

5.4.5. UF 6 mass spectrometers/ion sources

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of

taking "on-line" samples of feed, product or tails, from UF 6 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 UF 6 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, UF 6 -resistant materials. For the purposes

of the sections relating to gaseous diffusion items the materials resistant to corrosion by

UF 6 include stainless steel, aluminium, aluminium alloys, aluminium oxide, nickel or

alloys containing 60% or more nickel and UF 6 -resistant fully fluorinated hydrocarbon

polymers.

Especially designed or prepared systems, equipment and components for use in

aerodynamic enrichment plants

INTRODUCTORY NOTE

In aerodynamic enrichment processes, a mixture of gaseous UF 6 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 UF 6 , all equipment, pipeline and instrumentation surfaces (that come in

contact with the gas) must be made of materials that remain stable in contact with UF 6 .

EXPLANATORY NOTE

The items listed in this section either come into direct contact with the UF 6 process gas or

directly control the flow within the cascade. All surfaces which come into contact with

the process gas are wholly made of or protected by UF 6 -resistant materials. For the

purposes of the section relating to aerodynamic enrichment items, the materials resistant

to corrosion by UF 6 include copper, stainless steel, aluminium, aluminium alloys, nickel

or alloys containing 60% or more nickel and UF 6 -resistant fully fluorinated hydrocarbon

polymers.

5.5.1. Separation nozzles

Especially designed or prepared separation nozzles and assemblies thereof. The

separation nozzles consist of slit-shaped, curved channels having a radius of curvature

less than 1 mm (typically 0.1 to 0.05 mm), resistant to corrosion by UF 6 and having a

knife-edge within the nozzle that separates the gas flowing through the nozzle into two

fractions.

5.5.2. Vortex tubes

Especially designed or prepared vortex tubes and assemblies thereof. The vortex tubes

are cylindrical or tapered, made of or protected by materials resistant to corrosion by UF 6 ,

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.

5.5.3. Compressors and gas blowers

Especially designed or prepared axial, centrifugal or positive displacement compressors

or gas blowers made of or protected by materials resistant to corrosion by UF 6 and with a

suction volume capacity of 2 m 3 /min or more of UF 6 /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.

5.5.4. Rotary shaft seals

Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust

connections, for sealing the shaft connecting the compressor rotor or the gas blower rotor

with the driver motor so as to ensure a reliable seal against out-leakage of process gas or

in-leakage of air or seal gas into the inner chamber of the compressor or gas blower

which is filled with a UF 6 /carrier gas mixture.

5.5.5. Heat exchangers for gas cooling

Especially designed or prepared heat exchangers made of or protected by materials

resistant to corrosion by UF 6 .

5.5.6. Separation element housings

Especially designed or prepared separation element housings, made of or protected by

materials resistant to corrosion by UF 6 , 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.

5.5.7. Feed systems/product and tails withdrawal systems

Especially designed or prepared process systems or equipment for enrichment plants

made of or protected by materials resistant to corrosion by UF 6 , including

(a)

Feed autoclaves, ovens, or systems used for passing UF 6 to the enrichment

process;

(b)

Desublimers (or cold traps) used to remove UF 6 from the enrichment process for

subsequent transfer upon heating;

(c)

Solidification or liquefaction stations used to remove UF 6 from the enrichment

process by compressing and converting UF 6 to a liquid or solid form;

(d)

'Product' or 'tails' stations used for transferring UF 6 into containers.

5.5.8. Header piping systems

Especially designed or prepared header piping systems, made of or protected by materials

resistant to corrosion by UF 6 , for handling UF 6 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.

5.5.9. Vacuum systems and pumps

(a)

Especially designed or prepared vacuum systems having a suction capacity of 5

m 3 /min or more, consisting of vacuum manifolds, vacuum headers and vacuum pumps,

and designed for service in UF 6 -bearing atmospheres,

(b)

Vacuum pumps especially designed or prepared for service in UF 6 -bearing

atmospheres and made of or protected by materials resistant to corrosion by UF 6 . These

pumps may use fluorocarbon seals and special working fluids.

5.5.10. Special shut-off and control valves

Especially designed or prepared manual or automated shut-off and control bellows valves

made of or protected by materials resistant to corrosion by UF 6 with a diameter of 40 to

1500 mm for installation in main and auxiliary systems of aerodynamic enrichment

plants.

5.5.11. UF 6 mass spectrometers/ion sources

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of

taking 'on-line' samples of feed, 'product' or 'tails', from UF 6 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.

5.5.12. UF 6 /carrier gas separation systems

Especially designed or prepared process systems for separating UF 6 from carrier gas

(hydrogen or helium).

EXPLANATORY NOTE

These systems are designed to reduce the UF 6 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 UF 6 from carrier gas,

or

(d)

UF 6 cold traps capable of temperatures of -20 o C or less.

Especially designed or prepared systems, equipment and components for use in

chemical exchange or ion exchange enrichment plants

INTRODUCTORY NOTE

The slight difference in mass between the isotopes of uranium causes small changes in

chemical reaction equilibria that can be used as a basis for separation of the isotopes.

Two processes have been successfully developed: liquid-liquid chemical exchange and

solid-liquid ion exchange.

In the liquid-liquid chemical exchange process, immiscible liquid phases (aqueous and

organic) are countercurrently contacted to give the cascading effect of thousands of

separation stages. The aqueous phase consists of uranium chloride in hydrochloric acid

solution; the organic phase consists of an extractant containing uranium chloride in an

organic solvent. The contactors employed in the separation cascade can be liquidliquid

exchange columns (such as pulsed columns with sieve plates) or liquid centrifugal

contactors. Chemical conversions (oxidation and reduction) are required at both ends of

the separation cascade in order to provide for the reflux requirements at each end. A

major design concern is to avoid contamination of the process streams with certain metal

ions. Plastic, plastic-lined (including use of fluorocarbon polymers) and/or glass-lined

columns and piping are therefore used.

In the solid-liquid ion-exchange process, enrichment is accomplished by uranium

adsorption/desorption on a special, very fast-acting, ion-exchange resin or adsorbent. A

solution of uranium in hydrochloric acid and other chemical agents is passed through

cylindrical enrichment columns containing packed beds of the adsorbent. For a

continuous process, a reflux system is necessary to release the uranium from the dsorbent

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

corrosion-resistant materials.

5.6.1. Liquid-liquid exchange columns (Chemical exchange)

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 corrosion resistance 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).

5.6.2. Liquid-liquid centrifugal contactors (Chemical exchange)

Liquid-liquid centrifugal contactors especially designed or prepared for uranium

enrichment using the chemical exchange process. Such contactors use rotation to achieve

dispersion of the organic and aqueous streams and then centrifugal force to separate the

phases. For corrosion resistance to concentrated hydrochloric acid solutions, the

contactors are 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).

5.6.3. Uranium reduction systems and equipment (Chemical exchange)

(a)

Especially designed or prepared electrochemical reduction cells to reduce

uranium from one valence state to another for uranium enrichment using the chemical

exchange process. The cell materials in contact with process solutions must be corrosion

resistant to concentrated hydrochloric acid solutions.

EXPLANATORY NOTE

The cell cathodic compartment must be designed to prevent re-oxidation of uranium to its

higher valence state. To keep the uranium in the cathodic compartment, the cell may have

an impervious diaphragm membrane constructed of special cation exchange material. The

cathode consists of a suitable solid conductor such as graphite.

(b)

Especially designed or prepared systems at the product end of the cascade for

taking the U 4+ out of the organic stream, adjusting the acid concentration and feeding to

the electrochemical reduction cells.

EXPLANATORY NOTE

These systems consist of solvent extraction equipment for stripping the U 4+ from the

organic stream into an aqueous solution, evaporation and/or other equipment to

accomplish solution pH adjustment and control, and pumps or other transfer devices for

feeding to the electrochemical reduction cells. A major design concern is to avoid

contamination of the aqueous stream with certain metal ions. Consequently, for those

parts in contact with the process stream, the system is constructed of equipment made of

or protected by suitable materials (such as glass, fluorocarbon polymers, polyphenyl

sulfate, polyether sulfone, and resin-impregnated graphite).

5.6.4. Feed preparation systems (Chemical exchange)

Especially designed or prepared systems for producing high-purity uranium chloride

feed solutions for chemical exchange uranium isotope separation plants.

EXPLANATORY NOTE

These systems consist of dissolution, solvent extraction and/or ion exchange equipment

for purification and electrolytic cells for reducing the uranium U 6+ or U 4+ to U 3+ . These

systems produce uranium chloride solutions having only a few parts per million of

metallic impurities such as chromium, iron, vanadium, molybdenum and other bivalent or

higher multi-valent cations. Materials of construction for portions of the system

processing high-purity U 3+ include glass, fluorocarbon polymers, polyphenyl sulfate or

polyether sulfone plastic-lined and resin-impregnated graphite.

5.6.5. Uranium oxidation systems (Chemical exchange)

Especially designed or prepared systems for oxidation of U 3+ to U 4+ for return to the

uranium isotope separation cascade in the chemical exchange enrichment process.

EXPLANATORY NOTE

These systems may incorporate equipment such as

(a)

Equipment for contacting chlorine and oxygen with the aqueous effluent from the

isotope separation equipment and extracting the resultant U 4+ into the stripped organic

stream returning from the product end of the cascade,

(b)

Equipment that separates water from hydrochloric acid so that the water and the

oncentrated hydrochloric acid may be reintroduced to the process at the proper locations.

5.6.6. Fast-reacting ion exchange resins/adsorbents (ion exchange)

Fast-reacting ion-exchange resins or adsorbents especially designed or prepared for

uranium enrichment using the ion exchange process, including porous macroreticular

resins, and/or pellicular structures in which the active chemical exchange groups are

limited to a coating on the surface of an inactive porous support structure, and other

composite structures in any suitable form including particles or fibers. These ion

exchange resins/adsorbents have diameters of 0.2 mm or less and must be chemically

resistant to concentrated hydrochloric acid solutions as well as physically strong ough 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.

5.6.7. Ion exchange columns (Ion exchange)

Cylindrical columns greater than 1000 mm in diameter for containing and supporting

packed beds of ion exchange resin/adsorbent, especially designed or prepared for

uranium enrichment using the ion exchange process. These columns are made of or

protected by materials (such as titanium or fluorocarbon plastics) resistant to corrosion by

concentrated hydrochloric acid solutions and are capable of operating at a temperature in

the range of 100 o C to 200 o C and pressures above 0.7 MPa (102 psia).

5.6.8. Ion exchange reflux systems (Ion exchange)

(a)

Especially designed or prepared chemical or electrochemical reduction systems

for regeneration of the chemical reducing agent(s) used in ion exchange uranium

enrichment cascades.

(b)

Especially designed or prepared chemical or electrochemical oxidation systems

for regeneration of the chemical oxidizing agent(s) used in ion exchange uranium

enrichment cascades.

EXPLANATORY NOTE

The ion exchange enrichment process may use, for example, trivalent titanium (Ti 3+ ) as a

reducing cation in which case the reduction system would regenerate Ti 3+ by reducing

Ti 4+ .

The process may use, for example, trivalent iron (Fe 3+ ) as an oxidant in which case the

oxidation system would regenerate Fe 3+ by oxidizing Fe 2+ .

Especially designed or prepared systems, equipment and components for use in

laser-based enrichment plants

INTRODUCTORY NOTE

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.

EXPLANATORY NOTE

Many of the items listed in this section come into direct contact with uranium metal

vapor or liquid or with process gas consisting of UF 6 or a mixture of UF 6 and other gases.

All surfaces that come into contact with the uranium or UF 6 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 UF 6 include copper, stainless steel, aluminium,

aluminium alloys, nickel or alloys containing 60 % or more nickel and UF 6 -resistant fully

fluorinated hydrocarbon polymers.

5.7.1. Uranium vaporization systems (AVLIS)

Especially designed or prepared uranium vaporization systems which contain highpower

strip or scanning electron beam guns with a delivered power on the target of more than

2.5 kW/cm.

5.7.2. Liquid uranium metal handling systems (AVLIS)

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.

5.7.3. Uranium metal 'product' and 'tails' collector assemblies (AVLIS)

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.

5.7.4. Separator module housings (AVLIS)

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 feed-throughs, laser

beam windows, vacuum pump connections and instrumentation diagnostics and

monitoring. They have provisions for opening and closure to allow refurbishment of

internal components.

5.7.5. Supersonic expansion nozzles (MLIS)

Especially designed or prepared supersonic expansion nozzles for cooling mixtures of

UF 6 and carrier gas to 150 K or less and which are corrosion resistant to UF 6 .

5.7.6. Uranium pentafluoride product collectors (MLIS)

Especially designed or prepared uranium pentafluoride (UF 5 ) solid product collectors

consisting of filter, impact, or cyclone-type collectors, or combinations thereof, and

which are corrosion resistant to the UF 5 /UF 6 environment.

5.7.7. UF 6 /carrier gas compressors (MLIS)

Especially designed or prepared compressors for UF 6 /carrier gas mixtures, designed for

long term operation in a UF 6 environment. The components of these compressors that

come into contact with process gas are made of or protected by materials resistant to

corrosion by UF 6 .

5.7.8. Rotary shaft seals (MLIS)

Especially designed or prepared rotary shaft seals, with seal feed and seal exhaust

connections, for sealing the shaft connecting the compressor rotor with the driver motor

so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or

seal gas into the inner chamber of the compressor which is filled with a UF 6 /carrier gas

mixture.

5.7.9. Fluorination systems (MLIS)

Especially designed or prepared systems for fluorinating UF 5 (solid) to UF 6 (gas).

EXPLANATORY NOTE

These systems are designed to fluorinate the collected UF 5 powder to UF 6 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 UF 5 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 UF 6 are

used.

5.7.10. UF 6 mass spectrometers/ion sources (MLIS)

Especially designed or prepared magnetic or quadrupole mass spectrometers capable of

taking 'on-line' samples of feed, 'product' or 'tails', from UF 6 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.

Feed systems/product and tails withdrawal systems (MLIS)

Especially designed or prepared process systems or equipment for enrichment plants

made of or protected by materials resistant to corrosion by UF 6 , including

(a)

Feed autoclaves, ovens, or systems used for passing UF 6 to the enrichment

process

(b)

Desublimers (or cold traps) used to remove UF 6 from the enrichment process for

subsequent transfer upon heating;

(c)

Solidification or liquefaction stations used to remove UF 6 from the enrichment

process by compressing and converting UF 6 to a liquid or solid form;

Product' or 'tails' stations used for transferring UF 6 into containers.

5.7.12. UF 6 /carrier gas separation systems (MLIS)

Especially designed or prepared process systems for separating UF 6 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 -120 o C

or less, or

(b)

Cryogenic refrigeration units capable of temperatures of -120 o C or less, or

(c)

UF 6 cold traps capable of temperatures of -20 o C or less.

5.7.13. Laser systems (AVLIS, MLIS and CRISLA)

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 CO 2 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.

Especially designed or prepared systems, equipment and components for use in

ation enrichment plants

INTRODUCTORY NOTE

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 corkscrew-like 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'.

5.8.1. Microwave power sources and antennae

Especially designed or prepared microwave power sources and antennae for producing or

accelerating ions and having the following characteristics: greater than 30 GHz frequency

and greater than 50 kW mean power output for ion production.

5.8.2. Ion excitation coils

Especially designed or prepared radio frequency ion excitation coils for frequencies of

more than 100 kHz and capable of handling more than 40 kW mean power.

5.8.3. Uranium plasma generation systems

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.

5.8.4. Liquid uranium metal handling systems

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.

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

Especially designed or prepared 'product' and 'tails' collector assemblies for uranium

metal in solid form. These collector assemblies are made of or protected by materials

resistant to the heat and corrosion of uranium metal vapor, such as yttria-coated graphite

or tantalum.

5.8.6. Separator module housings

Cylindrical vessels especially designed or prepared for use in plasma separation

enrichment plants for containing the uranium plasma source, radio-frequency drive coil

and the 'product' and 'tails' collectors.

EXPLANATORY NOTE

These housings have a multiplicity of ports for electrical feed-throughs, diffusion pump

connections and instrumentation diagnostics and monitoring. They have provisions for

opening and closure to allow for refurbishment of internal components and are

constructed of a suitable non-magnetic material such as stainless steel.

5.9. Especially designed or prepared systems, equipment and components for use

in electromagnetic enrichment plants

INTRODUCTORY NOTE

In the electromagnetic process, uranium metal ions produced by ionization of a salt feed

material (typically UCl 4 ) 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.

5.9.1. Electromagnetic isotope separators

Electromagnetic isotope separators especially designed or prepared for the separation of

uranium isotopes, and equipment and components therefor, including

(a)

Ion sources

Especially designed or prepared single or multiple uranium ion sources consisting

of a 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

(c)

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.

(d)

Vacuum housings

(e)

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.

(c)

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.

5.9.2. High voltage power supplies

Especially designed or prepared high-voltage power supplies for ion sources, having all

of the following characteristics: capable of continuous operation, output voltage of

20,000 V or greater, output current of 1 A or greater, and voltage regulation of better than

0.01% over a time period of 8 hours.

5.9.3. Magnet power supplies

Especially designed or prepared high-power, direct current magnet power supplies having

all of the following characteristics: capable of continuously producing a current output of

500 A or greater at a voltage of 100 V or greater and with a current or voltage regulation

better than 0.01% over a period of 8 hours.

6. Plants for the production of heavy water, deuterium and deuterium compounds and

equipment especially designed or prepared therefor

INTRODUCTORY NOTE

Heavy water can be produced by a variety of processes. However, the two processes that

have proven to be commercially viable are the water-hydrogen sulphide exchange

process (GS process) and the ammonia-hydrogen 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.

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.

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.

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

Water - Hydrogen Sulphide Exchange Towers

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 waterhydrogen sulphide exchange

process.

Blowers and Compressors

Single stage, low head (i.e., 0.2 MPa or 30 psi) centrifugal blowers or compressors for

hydrogen-sulphide gas circulation (i.e., gas containing more than 70% H 2 S) 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 m 3 /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 H 2 S service.

Ammonia-Hydrogen Exchange Towers

Ammonia-hydrogen exchange towers greater than or equal to 35 m (114.3 ft) in height

with diameters of 1.5 m (4.9 ft) to 2.5 m (8.2 ft) capable of operating at pressures greater

than 15 MPa (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.

Tower Internals and Stage Pumps

Tower internals and stage pumps especially designed or prepared for towers for heavy

water production utilizing the ammonia-hydrogen exchange process. Tower internals

include especially designed stage contactors which promote intimate gas/liquid contact.

Stage pumps include especially designed submersible pumps for circulation of liquid

ammonia within a contacting stage internal to the stage towers.

Ammonia Crackers

Ammonia crackers with operating pressures greater than or equal to 3 MPa (450 psi)

especially designed or prepared for heavy water production utilizing the ammonia

hydrogen exchange process.

Infrared Absorption Analyzers

Infrared absorption analyzers capable of "on-line" hydrogen/deuterium ratio analysis

where deuterium concentrations are equal to or greater than 90%.

Catalytic Burners

Catalytic burners for the conversion of enriched deuterium gas into heavy water

especially designed or prepared for heavy water production utilizing the ammonia

hydrogen exchange process.

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

prepared therefor

INTRODUCTORY NOTE

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 UO 3 , conversion of UO 3 to UO 2 , conversion of uranium oxides to UF 4 or

UF 6 , conversion of UF 4 to UF 6 , conversion of UF 6 to UF 4 , conversion of UF 4 to uranium

metal, and conversion of uranium fluorides to UO 2 . 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 liquid-liquid extraction columns. However, few of the items are

available "off-the-shelf"; 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, F 2 , ClF 3 , 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.

Especially designed or prepared systems for the conversion of uranium ore

concentrates to UO 3

EXPLANATORY NOTE

Conversion of uranium ore concentrates to UO 3 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 UO 3 either by concentration and

denitration or by neutralization with gaseous ammonia to produce ammonium diuranate

with subsequent filtering, drying, and calcining.

Especially designed or prepared systems for the conversion of UO 3 to UF 6

EXPLANATORY NOTE

Conversion of UO 3 to UF 6 can be performed directly by fluorination. The process requires

a source of fluorine gas or chlorine trifluoride.

Especially designed or prepared systems for the conversion of UO 3 to UO 2

EXPLANATORY NOTE

Conversion of UO 3 to UO 2 can be performed through reduction of UO 3 with cracked

ammonia gas or hydrogen.

Especially designed or prepared systems for the conversion of UO 2 to UF 4

EXPLANATORY NOTE

Conversion of UO 2 to UF 4 can be performed by reacting UO 2 with hydrogen fluoride gas

(HF) at 300-500 o C.

Especially designed or prepared systems for the conversion of UF 4 to UF 6

EXPLANATORY NOTE

Conversion of UF 4 to UF 6 is performed by exothermic reaction with fluorine in a tower

reactor. UF 6 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.

Especially designed or prepared systems for the conversion of UF 4 to U metal

EXPLANATORY NOTE

Conversion of UF 4 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 o C).

7.7.

Especially designed or prepared systems for the conversion of UF 6 to UO 2

EXPLANATORY NOTE

Conversion of UF 6 to UO 2 can be performed by one of three processes. In the first, UF 6 is

reduced and hydrolyzed to UO 2 using hydrogen and steam. In the second, UF 6 is

hydrolyzed by solution in water, ammonia is added to precipitate ammonium diuranate,

and the diuranate is reduced to UO 2 with hydrogen at 820 o C. In the third process,

gaseous UF 6 , CO 2 , and NH 3 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 UO 2 .

UF 6 to UO 2 conversion is often performed as the first stage of a fuel fabrication plant.

Especially designed or prepared systems for the conversion of UF 6 to UF 4

EXPLANATORY NOTE

Conversion of UF 6 to UF 4 is performed by reduction with hydrogen.