Additional Protocol to the Agreement between the Republic of Austria, the Kingdom of Belgium, the Kingdom of Denmark, the Republic of Finland, the Federal Republic of Germany, the Hellenic Republic, Ireland, the Italian Republic, the Grand Duchy of Luxembourg, the Kingdom of the Netherlands, the Portuguese Republic, the Kingdom of Spain, the Kingdom of Sweden, the European Atomic Energy Community and the International Atomic Energy Agency in implementation of Article III(1) and (4) of the Treaty on the Non-proliferation of Nuclear weapons (notified under document number COM(1998) 314)
Date: 1998-09-22
Institutions: Austria, Belgium, Denmark, European Atomic Energy Community, Finland, Germany, Greece, International Atomic Energy Agency, Ireland, Italy, Luxembourg, Netherlands, Portugal, Spain, Sweden
Subjects: International Atomic Energy Agency, agreement (EU), arms limitation, nuclear energy, nuclear safety, nuclear weapon, protocol to an agreement

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II

(Acts  whose  publication  is  not  obligatory)

COMMISSION

ADDITIONAL  PROTOCOL

to  the  Agreement  between  the  Republic  of  Austria,  the  Kingdom  of  Belgium,  the  Kingdom  of
Denmark,  the  Republic  of  Finland,  the  Federal  Republic  of  Germany,  the  Hellenic  Republic,
Ireland,  the  Italian  Republic,  the  Grand  Duchy  of  Luxembourg,  the  Kingdom  of  the
Netherlands,  the  Portuguese  Republic,  the  Kingdom  of  Spain,  the  Kingdom  of  Sweden,  the
European  Atomic  Energy  Community  and  the  International  Atomic  Energy  Agency  in
implementation  of  Article  III(1)  and  (4)  of  the  Treaty  on  the  Non-proliferation  of  Nuclear
weapons (*)

(notified  under  document  number  COM(1998)  314)

(1999/188/Euratom)

PREAMBLE

Whereas  the  Republic  of  Austria,  the  Kingdom  of  Belgium,  the  Kingdom  of  Denmark,  the  Republic  of
Finland,  the  Federal  Republic  of  Germany,  the  Hellenic  Republic,  Ireland,  the  Italian  Republic,  the  Grand
Duchy  of  Luxembourg,  the  Kingdom  of  the  Netherlands,  the  Portuguese  Republic,  the  Kingdom  of  Spain,
the  Kingdom  of  Sweden  (hereinafter  referred  to  as  ‘the  States’)  and  the  European  Atomic  Energy
Community (hereinafter referred to as ‘the Community’) are parties to an Agreement between the States, the
Community  and  the  International  Atomic  Energy  Agency  (hereinafter  referred  to  as  the  ‘the  Agency’)  in
implementation  of  Article  III(1)  and  (4)  of  the  Treaty  on  the  Non-proliferation  of  Nuclear  Weapons
(hereinafter  referred  to  as  the  ‘Safeguards  Agreement’),  which  entered  into  force  on  21  February  1997;

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  in  the  Community  or  international  cooperation
safety,  physical  protection
in 

field  of  peaceful  nuclear  activities, 

respect  health, 

the 

to 

(*) On  8  June  1998,  the  Council  approved  the  conclusion  by  the  Commission  on  behalf  of  the  European
Atomic  Energy  Community  (the  Community)  not  only  of  this  Additional  Protocol  to  the  Agreement
between  the  13  non-nuclear-weapon  Member  States  of  the  Community,  the  Community  and  the  IAEA
(published in OJ L 51 Volume 21, dated 22 February 1978 and as IAEA document INFCIRC/193, dated
14  September  1973)  but  also  Additional  Protocols  to  the  Agreements  between  the  United  Kingdom  of
Great  Britain  and  Northern  Ireland,  the  Community  and  the  IAEA  (published  as  IAEA  document
INFCIRC/263,  dated  October  1978)  and  between  France,  the  Community  and  the  IAEA  (published  as
IAEA  document  INFCIRC/290,  dated  December  1981).  All  three  Additional  Protocols  were  signed  by
the  relevant  Parties  in  Vienna  on  22  September  1998.  The  texts  of  each  Additional  Protocol  can  be
accessed  at  the  following  internet  address:  http://europa.eu.int/en/comm/dg17/nuclear/nuchome.htm

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and other security provisions in force and the rights of individuals, and to 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  the  Community,  the  States  and  the  Agency  have  agreed  as  follows:

RELATIONSHIP  BETWEEN  THE  THE  PROTOCOL  AND
THE  SAFEGUARDS  AGREEMENT

(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.

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

(a)  Each  State  shall  provide 

the  Agency  with  a
declaration  containing  the  information  identified  in
sub-paragraphs  (i),  (ii),  (iv),  (ix)  and  (x).  The
Community  shall  provide 
the  Agency  with  a
declaration  containing  the  information  identified  in
sub-paragraphs  (v),  (vi)  and  (vii).  Each  State  and  the
the  Agency  with  a
Community  shall  provide 
declaration  containing  the  information  identified  in
sub-paragraphs  (iii)  and  (viii).

location  of  nuclear 

(i)  A  general  description  of  and 
the 

information
specifying 
fuel
cycle-related research and development activities
involving  nuclear  material  carried  out
not 
anywhere 
specifically
authorised  or  controlled  by,  or  carried  out  on
behalf  of,  the  State  concerned.

funded, 

that 

are 

(ii) 

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

(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 in each
State,  and  the  current  annual  production  of
such  mines  and  concentration  plants.  The
Community  shall  provide,  on  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  the  States  at  which  the
material  is  present  in  quantities  exceeding
10  tonnes  of  uranium  and/or  20  tonnes  of
thorium,  and  for  other 
locations  with
quantities  of  more  than  1  tonne,  the
aggregate  for  the  States  as  a  whole  if  the
aggregate  exceeds  10  tonnes  of  uranium  or
20  tonnes  of  thorium.  The  provision  of  this
information  does  not 
require  detailed
nuclear  material  accountancy;

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(b) The  quantities,  the  chemical  composition
and the destination of each export from the
States  to  a  State  outside  the  Community,  of
such  material  for  specifically  non-nuclear
purposes  in  quantities  exceeding:

(1) 10  tonnes  of  uranium,  or  for  successive
exports  of  uranium  to  the  same  state,
tonnes,  but
each  of 
exceeding  a  total  of  10  tonnes  for  the
year;

than  10 

less 

(2) 20  tonnes  of  thorium,  or  for  successive
exports  of  thorium  to  the  same  State,
each  of 
tonnes,  but
exceeding  a  total  20  tonnes  for  the
year;

than  20 

less 

(c)  the 

chemical 

quantities, 

composition,
current  location  and  use  or  intended  use  of
each  import  into  the  Sates  from  outside  the
Community  of  such  material  for  specifically
non-nuclear 
quantities
exceeding:

purposes 

in 

(1) 10  tonnes  of  uranium,  or  for  successive
imports of uranium each of less than 10
tonnes,  but  exceeding  a  total  of  10
tonnes  for  the  year;

(2) 20  tonnes  of  thorium,  or  for  successive
imports  of  thorium  each  of  less  than  20
tonnes,  but  exceeding  a  total  of  20
tonnes  for  the  year;

it  being  understood 
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.

there 

that 

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

the  waste  or 

its 

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

(a)  for  each  export  out  of  the  Community  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) on 

specific 

request  by 

the  Agency,
confirmation  by  the 
importing  State  of
information  provided  to  the  Agency  by  a
State  outside  of  the  Community  concerning
the  export  of  such  equipment  and  material
to  the  importing  State.

(x)  General plans for the succeeding 10-year period
relevant  to  the  development  of  the  nuclear  fuel
fuel
cycle 
cycle-related 
development
activities)  when  approved  by  the  appropriate
authorities  in  the  State.

(including 

research 

planned 

nuclear 

and 

(vii)  (a)  Information  regarding  the  quantities,  uses
and  locations  of  nuclear  material  exempted
from  safeguards  pursuant  to  Article  37  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 36(b) of
the  Safeguards  Agreement  but  not  yet  in  a
in  quantities
non-nuclear  end-use  form, 
exceeding  those  set  out  in  Article  37  of  the
Safeguards Agreement. The provision of this
information  does  not 
require  detailed
nuclear  material  accountancy.

(b) Each  State  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 the
State  concerned  but  which  are  not  funded,
specifically authorised or controlled by, or carried
out  on  behalf  of,  that  State.  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.

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(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.

(c)  On request by any or all of the Agency, a State or the
Community, 
provide
amplifications  or  clarifications  of  any  information
provided  under  this  Article,  in  so  far  as  relevant  for
the  purpose  of  safeguards.

appropriate, 

shall 

as 

Article  3

the  Community,  or  both,  as
(a)  Each  State  or 
appropriate, 
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.

shall  provide 

the  Agency 

to 

(b) Each  State  or 

the  Community,  or  both,  as
appropriate,  shall  provide  to  the  Agency,  by  15  May
of each year, updates of the information referred to in
paragraph  (a)  for  the  period  covering  the  previous
calendar  year.  If  there  has  been  no  change  to  the
information  previously  provided,  each  State  or  the
Community,  or  both,  as  appropriate,  shall  so
indicate.

(c)  The  Community  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.

(d) Each State shall provide to the Agency on a quarterly
basis  the  information  identified  in  Article  2(a)(ix)(a).
This  information  shall  be  provided  within  60  days  of
the  end  of  each  quarter.

(e)  The  Community  and  each  State  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.

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

(g)  Each  State 

shall  provide 

the
information  in  Article  2(a)(ix)(b)  within  60  days  of
the  Agency’s  request.

the  Agency 

to 

COMPLEMENTARY  ACCESS

Article  4

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

(a)  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
the 
information  provided
completeness  of 
pursuant 
resolve  an
to  Article  2  or 
inconsistency  relating  to  that  information;

to 

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

(b) (i)  Except as provided in paragraph (ii), the Agency
shall  give  the  State  concerned,  or  for  access
under  Article  5(a)  or  under  Article  5(c)  where
nuclear  material  is  involved,  the  State  concerned
and  the  Community,  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.

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

(d) In the case of a question or inconsistency, the Agency
shall provide the State concerned and, as appropriate,
the  Community  with  an  opportunity  to  clarify  and
facilitate 
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

resolution  of 

the 

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purpose  for  which  the  access  is  sought.  In  any  event,
the  Agency  shall  not  draw  any  conclusions  about  the
question  or  inconsistency  until  the  State  concerned
and,  as  appropriate,  the  Community  have  been
provided  with  such  an  opportunity.

(e)  Unless  otherwise  agreed  to  by  the  State  concerned,
access  shall  only  take  place  during  regular  working
hours.

(f)  The  State  concerned,  or  for  access  under  Article  5(a)
or  under  Article  5(c)  where  nuclear  material  is
involved,  the  State  concerned  and  the  Community,
shall  have  the  right  to  have  agency 
inspectors
accompanied during their access by its representatives
and,  as  appropriate,  by  Community 
inspectors
provided  that  Agency  inspectors  shall  not  thereby  be
delayed  or  otherwise  impeded  in  the  exercise  of  their
functions.

Article  5

Each  State  shall  provide  the  Agency  with  access  to:

(a)  (i)  any  place  on  a  site;

(ii)  any  location  identified  under  Article  2(a)(v)  to

(viii);

(iii)  any  decommissioned  facility  or  decommissioned
location  outside  facilities  where  nuclear  material
was  customarily  used.

(b) Any  location  identified  by  the  State  concerned  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), provided that if the State concerned is unable to
provide  such  access,  that  State  shall  make  every
reasonable  effort  to  satisfy  Agency  requirements,
without  delay,  through  other  means.

(c)  Any  location  specified  by  the  Agency,  other  than
locations  referred  to  in  paragraphs  (a)  and  (b),  to
carry  out  location-specific  environmental  sampling,
provided  that  if  the  State  concerned  is  unable  to
provide  such  access,  that  State  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:

(a)  for  access  in  accordance  with  Article  5(a)(i)  or  (iii):
visual  observation;  collection  of  environmental

samples;  utilisation  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,  the  Community  and  the  State
concerned.

and 

(b) For  access  in  accordance  with  Article  5(a)(ii):  visual
observation; 
item  counting  of  nuclear  material;
sampling;
non-destructive  measurements 
utilisation  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,  the  Community  and  the  State
concerned.

examination 

(c)  For  access  in  accordance  with  Article  5(b):  visual
observation;  collection  of  environmental  samples;
utilisation  of  radiation  detection  and  measurement
devices; 
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  the  State  concerned.

safeguards 

of 

(d) 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), utilisation at that location of visual observation,
radiation  detection  and  measurement  devices,  and,  as
agreed  by  the  State  concerned  and,  where  nuclear
material is involved, the Community, and the Agency,
other  objective  measures.

Article  7

(a)  On request by a State, the Agency and that State 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  materials  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.

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(b) A State may, when providing the information referred
to  in  Article  2,  inform  the  Agency  of  the  places  at  a
site  or  location  at  which  managed  access  may  be
applicable.

(c)  Pending  the  entry 

into  force  of  any  necessary
Subsidiary  Arrangements,  a  State  may  have  recourse
to  managed  access  consistent  with  the  provisions  of
paragraph  (a).

Article  8

Nothing  in  this  Protocol  shall  preclude  a  State  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  on  such  a  request.

Article  9

Each  State  shall  provide  the  Agency  with  access  to
locations  specified  by  the  Agency  to  carry  out  wide-area
environmental sampling, provided that if a State is unable
to  provide  such  access  that  State  shall  make  every
reasonable  effort  to  satisfy  Agency  requirements  at
alternative  locations.  The  Agency  shall  not  seek  such
access  until  the  use  of  wide-area  environmental  sampling
and  the  procedural  arrangements  therefor  have  been
approved  by  the  Board  and  following  consultations
between  the  Agency  and  the  State  concerned.

Article  10

(a)  The  Agency  shall  inform  the  State  concerned  and,  as

appropriate,  the  Community  of:

(i)  the  activities  carried  out  under  this  Protocol,
including  those  in  respect  of  any  questions  or
inconsistencies  the  Agency  had  brought  to  the
attention  of 
the  State  concerned  and,  as
appropriate, the Community within 60 days of the
activities  being  carried  out  by  the  Agency.

(ii) The results of activities in respect of any questions
or  inconsistencies  the  Agency  had  brought  to  the
the  State  concerned  and,  as
attention  of 
appropriate,  the  Community  as  soon  as  possible
but in any case within 30 days of the results being
established  by  the  Agency.

(b) The  Agency  shall  inform  the  State  concerned  and  the
Community  of  the  conclusions  it  has  drawn  from  its
activities under this Protocol. The conclusions shall be
provided annually.

DESIGNATION  OF  AGENCY  INSPECTORS

Article  11

(a)  (i)  The  Director-General  shall  notify  the  Community
and  the  States  of  the  Board’s  approval  of  any
Agency  official  as  a  safeguards  inspector.  Unless
the  Community  advises  the  Director-General  of
the rejection of such an official as an inspector for
the  States  within  three  months  of  receipt  of
notification of the Board’s approval, the inspector
so notified to the Community and the States shall
be  considered  designated  to  the  States.

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

immediately 

inform 

shall 

(b) A  notification  referred  to  in  paragraph  (a)  shall  be
deemed  to  be  received  by  the  Community  and  the
States seven days after the date of the transmission by
registered  post  of  the  notification  by  the  Agency  to
the  Community  and  the  States.

VISAS

Article  12

the  designated 

therefor,  provide 
in 

Each  State  shall,  within  one  month  of  the  receipt  of  a
request 
inspector
the  request  with  appropriate  multiple
specified 
entry/exit  and/or  transit  visas,  where  required,  to  enable
the  inspector  to  enter  and  remain  on  the  territory  of  the
State  concerned  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  the  States.

SUBSIDIARY  ARRANGEMENTS

Article  13

(a)  Where  a  State  or  the  Community,  as  appropriate,  or
the  Agency  indicate  that  it  is  necessary  to  specify  in
subsidiary  Arrangements  how  measures  laid  down  in
this  Protocol  are  to  be  applied,  that  State,  or  that
State  and  the  Community  and  the  Agency  shall  agree
on  such  Subsidiary  Arrangements  within  90  days  of
the  entry  into  force  of  this  Protocol  or,  where  the

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the  need 

indication  of 
such  Subsidiary
Arrangements  is  made  after  the  entry  into  force  of
this  Protocol,  within  90  days  of  the  date  of  such
indication.

for 

(b) Pending  the  entry 

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

(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.

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

COMMUNICATIONS  SYSTEMS

Article  14

ANNEXES

Article  16

(a)  Each 

and 

shall 

State 

protect 

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

shall  be 

respect 

to 

in 

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

PROTECTION  OF  CONFIDENTIAL  INFORMATION

Article  15

(a)  The  Agency  shall  maintain  a  stringent  regime  to
ensure  effective  protection  against  disclosure  of
commercial,  technological  and  industrial  secrets  and
other 
its
knowledge, including such information coming to the
Agency’s  knowledge  in  the  implementation  of  this
Protocol.

information 

confidential 

coming 

to 

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

(b) The  list  of  activities  specified  in  Annex  I,  and  the  list
of equipment and material specified in Annex II, may
be  amended  by  the  Board  on  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.

(c)  Annex  III  to  this  Protocol  specifies  how  measures  in
this Protocol shall be implemented by the Community
and  the  States.

ENTRY  INTO  FORCE

Article  17

(a)  This  Protocol  shall  enter  into  force  on  the  day  on
which  the  Agency  receives  from  the  Community  and
the  States  written  notification  that  their  respective
requirements  for  entry  into  force  have  been  met.

(b) The  States  and  the  Community  may,  at  any  date
before  this  Protocol  enters  into  force,  declare  that
they  will  apply  this  Protocol  provisionally.

(c)  The  Director-General  shall  promptly 

inform  all
Member  States  of  the  Agency  of  any  declaration  of
provisional application of, and of the entry into force
of,  this  Protocol.

DEFINITIONS

Article  18

(b) The regime referred to in paragraph (a) shall include,

among  others,  provisions  relating  to:

For  the  purpose  of  this  Protocol:

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(a)  ‘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 

including 
or
(not 
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,

repackaging 

scientific 

research  or 

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

to 

(b) ‘Site’  means  that  area  delimited  by  the  Community
and  a  State  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 
facilities  where
location  outside 
nuclear  material  was  customarily  used  (this  is  limited
to  locations  with  hot  cells  or  where  activities  related
fabrication  or
to  conversion,  enrichment, 
reprocessing were carried out). ‘Site’ shall also include
all 
facility  or
location, for the provision or use of essential services,
including: hot cells for processing irradiated materials
not  containing  nuclear  material;  installations  for  the
treatment,  storage  and  disposal  of  waste;  and
buildings associated with specified activities identified
by  the  State  concerned  under  Article  2(a)(iv).

installations,  colocated  with 

fuel 

the 

(c)  ‘Decommissioned 

or 

facility‘ 

‘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  utilise  nuclear
material.

(d) ‘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.

(e)  ‘High  enriched  uranium’  means  uranium  containing

20 %  or  more  of  the  isotope  uranium-235.

(f)  ‘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.

(g)  ‘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.

(h) ‘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 on acceptance by
the  Community  and  the  States.

(i)  ‘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.

(j)  ‘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.

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L  67/9

Hecho  en  Viena,  por  duplicado,  el  veintidós  de  septiembre  de  mil  novecientos  noventa  y  ocho,
en las lenguas alemana, danesa, española, finesa, francesa, griega, inglesa, italiana, neerlandesa,
portuguesa  y  sueca  siendo  cada  uno  de  estos  textos  igualmente  aute´ntico,  si  bien,  en  caso  de
discrepancia, harán fe los textos acordados en las lenguas oficiales de la Junta de gobernadores
del  OIEA.

Udfærdiget  i  Wien  den  toogtyvende  september  nittenhundrede  og  otteoghalvfems  i  to
eksemplarer på dansk, engelsk, finsk, fransk, græsk, italiensk, nederlandsk, portugisisk, spansk,
svensk  og  tysk  med  samme  gyldighed  for  alle  versioner,  idet  teksterne  på  de  officielle
IAEA-sprog  dog  har  fortrinsstilling  i  tilfælde  af  uoverensstemmelser.

Geschehen  zu  Wien  am  22.  September  1998  in  zwei  Urschriften  in  dänischer,  deutscher,
englischer, finnischer, französischer, griechischer, italienischer, niederländischer, portugiesischer,
schwedischer  und  spanischer  Sprache,  wobei  jeder  Wortlaut  gleichermaßen  verbindlich,  im  Fall
von  unterschiedlichen  Auslegungen 
in  den  Amtssprachen  des
Gouverneursrats  der  Internationalen  Atomenergie-Organisation  maßgebend  ist.

jedoch  der  Wortlaut 

˛γØν(cid:229)  (cid:243)(cid:244)η  ΒØ(cid:229)(cid:139) ννη  (cid:229)Øς  (cid:228)Ø(cid:240)λ(cid:239)υ(cid:139) ν,  (cid:244)ην  22η  ηµ(cid:229)(cid:139) ρÆ  (cid:244)(cid:239)υ  Σ(cid:229)(cid:240)(cid:244)(cid:229)µ(cid:226)ρ(cid:221)(cid:239)υ  1998,  (cid:243)(cid:244)η  (cid:228)ÆνØκη(cid:139) ,  (cid:239)λλÆν(cid:228)Øκη(cid:139) ,
ÆγγλØκη(cid:139) ,  (cid:230)ØνλÆν(cid:228)Øκη(cid:139) ,  γÆλλØκη(cid:139) ,  γ(cid:229)ρµÆνØκη(cid:139) ,  (cid:229)λληνØκη(cid:139) ,  Ø(cid:244)ÆλØκη(cid:139) ,  (cid:240)(cid:239)ρ(cid:244)(cid:239)γÆλØκη(cid:139) ,  Ø(cid:243)(cid:240)ÆνØκη(cid:139) κÆØ  (cid:243)(cid:239)υη(cid:228)Øκη(cid:139)
γλω(cid:139) (cid:243)(cid:243)Æﬂ  (cid:244)Æ  κ(cid:229)(cid:221)µ(cid:229)νÆ  (cid:243)(cid:229)  (cid:222)λ(cid:229)ς  (cid:244)Øς  Æνω(cid:244)(cid:229)(cid:139) ρω  γλω(cid:139) (cid:243)(cid:243)(cid:229)ς  (cid:229)(cid:221)νÆØ  (cid:229)Œ(cid:221)(cid:243)(cid:239)υ  Æυθ(cid:229)ν(cid:244)Øκ(cid:192),  (cid:229)κ(cid:244)(cid:222)ς  Æ(cid:240)(cid:222)  (cid:240)(cid:229)ρ(cid:221)(cid:240)(cid:244)ω(cid:243)η
Æ(cid:240)(cid:222)κλØ(cid:243)ης,  (cid:239)(cid:240)(cid:222)(cid:244)(cid:229)  υ(cid:240)(cid:229)ρØ(cid:243)łυ(cid:139) (cid:239)υν  (cid:244)Æ  κ(cid:229)(cid:221)µ(cid:229)νÆ  (cid:240)(cid:239)υ  (cid:229)(cid:139) ł(cid:239)υν  (cid:243)υν(cid:244)Æłθ(cid:229)(cid:221)  (cid:243)(cid:244)Øς  (cid:229)(cid:240)(cid:221)(cid:243)ηµ(cid:229)ς  γλω(cid:139) (cid:243)(cid:243)(cid:229)ς  (cid:244)(cid:239)υ
∆Ø(cid:239)Øκη(cid:244)Øκ(cid:239)υ(cid:139) Συµ(cid:226)(cid:239)υλ(cid:221)(cid:239)υ  (cid:244)(cid:239)υ  ∆Ø(cid:229)θν(cid:239)υ(cid:139) ς  ˆργÆνØ(cid:243)µ(cid:239)υ(cid:139) Α(cid:244)(cid:239)µØκη(cid:139) ς Εν(cid:229)(cid:139) ργ(cid:229)ØÆς.

Done  at  Vienna  in  duplicate,  on  the  twenty  second  day  of  September  1998  in  the  Danish,
Dutch,  English,  Finnish,  French,  German,  Greek,  Italian,  Portuguese,  Spanish  and  Swedish
languages, the texts of which are equally authentic except that, in case of divergence, those texts
concluded  in  the  official  languages  of  the  IAEA  Board  of  Governors  shall  prevail.

Fait  à  Vienne,  en  deux  exemplaires  le  22  septembre  1998  en  langues  allemande,  anglaise,
danoise,  espagnole,  finnoise,  française,  grecque,  italienne,  ne´erlandaise,  portugaise  et  sue´doise;
tous  ces  textes  font  e´galement foi sauf que, en cas de divergence, les versions conclues dans les
langues  officielles  du  Conseil  des  gouverneurs  de  l’AIEA  pre´valent.

Fatto  a  Vienna  in  duplice  copia,  il  giorno  22  del  mese  di  settembre  1998  nelle  lingue  danese,
finnico,  francese,  greco,  inglese,  italiano,  olandese,  portoghese,  spagnolo,  svedese  e  tedesco,
ognuna  delle  quali  facente  ugualmente  fede,  ad  eccezione  dei  testi  conclusi  nelle  lingue  ufficiali
del  Consiglio  dei  governatori  dell’AIEA  che  prevalgono  in  caso  di  divergenza  tra  i  testi.

Gedaan te Wenen op 22 september 1998, in tweevoud, in de Deense, de Duitse, de Engelse, de
Finse,  de  Franse,  de  Griekse,  de  Italiaanse,  de  Nederlandse,  de  Portugese,  de  Spaanse  en  de
Zweedse  taal,  zijnde  alle  teksten  gelijkelijk  authentiek,  met  dien  verstande  dat  in  geval  van
tegenstrijdigheid  de  teksten  die  zijn  gesloten  in  de  officiële  talen  van  de  IOAE  bindend  zijn.

Feito  em  Viena  em  duplo  exemplar,  aos  vinte  e  dois  de  Setembro  de  1998  em  língua  alemã,
dinamarquesa, espanhola, finlandesa, francesa, grega, inglesa, italiana, neerlandesa, portuguesa e
sueca;  todos  os  textos  fazem  igualmente  fe´ mas,  em  caso  de  divergeˆncia,  prevalecem  aqueles
textos  que  tenham  sido  estabelecidos  em  línguas  oficiais  do  Conselho  dos  Governadores  da
AIEA.

Tehty  Wienissä  kahtena  kappaleena  22  päivänä  syyskuuta  1998  tanskan,  hollannin,  englannin,
suomen,  ranskan,  saksan,  kreikan,  italian,  portugalin,  espanjan  ja  ruotsin  kielellä;  kaikki
kieliversiot  ovat  yhtä  todistusvoimaisia,  mutta  eroavuuden  ilmetessä  on  noudatettava  niitä
tekstejä,  jotka  on  tehty  Kansainvälisen  atomienergiajärjestön  hallintoneuvoston  virallisilla
kielillä.

Utfärdat  i  Wien  i  två  exemplar  den  22  september  1998  på  danska,  engelska,  finska,  franska,
grekiska,  italienska,  nederländska,  portugisiska,  spanska,  svenska  och  tyska  språken,  varvid
varje  språkversion  skall  äga  lika  giltighet,  utom  ifall  de  skulle  skilja  sig  åt  då  de  texter  som
ingåtts  på  IAEA:s  styrelses  officiella  språk  skall  ha  företräde.

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13.3.1999

Por  el  Gobierno  del  Reino  de  Be´lgica

For  Kongeriget  Belgiens  regering

Für  die  Regierung  des  Königreichs  Belgien

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)(cid:239)υ  ΒÆ(cid:243)Øλ(cid:229)(cid:221)(cid:239)υ  (cid:244)(cid:239)υ  Β(cid:229)λγ(cid:221)(cid:239)υ

For  the  Government  of  the  Kingdom  of  Belgium

Pour  le  gouvernement  du  Royaume  de  Belgique

Per  il  governo  del  Regno  del  Belgio

Voor  de  regering  van  het  Koninkrijk  België

Pelo  Governo  do  Reino  da  Be´lgica

Belgian  kuningaskunnan  hallituksen  puolesta

För  Konungariket  Belgiens  regering

Mireille CLAEYS

Por  el  Gobierno  del  Reino  de  Dinamarca

For  Kongeriget  Danmarks  regering

Für  die  Regierung  des  Königreichs  Dänemark

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)(cid:239)υ  ΒÆ(cid:243)Øλ(cid:229)(cid:221)(cid:239)υ  (cid:244)(cid:239)υ  ∆Æν(cid:221)Æς

For  the  Government  of  the  Kingdom  of  Denmark

Pour  le  gouvernement  du  Royaume  de  Danemark

Per  il  governo  del  Regno  di  Danimarca

Voor  de  regering  van  het  Koninkrijk  Denemarken

Pelo  Governo  do  Reino  da  Dinamarca

Tanskan  kuningaskunnan  hallituksen  puolesta

För  Konungariket  Danmarks  regering

Henrik  WØHLK

13.3.1999

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L  67/11

Por  el  Gobierno  de  la  República  Federal  de  Alemania

For  Forbundsrepublikken  Tysklands  regering

Für  die  Regierung  der  Bundesrepublik  Deutschland

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  ˆµ(cid:239)(cid:243)(cid:240)(cid:239)ν(cid:228)ØÆκη(cid:139) ς  ∆ηµ(cid:239)κρÆ(cid:244)(cid:221)Æς  (cid:244)ης  Γ(cid:229)ρµÆν(cid:221)Æς

For  the  Government  of  the  Federal  Republic  of  Germany

Pour  le  gouvernement  de  la  Re´publique  fe´de´rale d’Allemagne

Per  il  governo  della  Repubblica  federale  di  Germania

Voor  de  regering  van  de  Bondsrepubliek  Duitsland

Pelo  Governo  da  República  Federal  da  Alemanha

Saksan  liittotasavallan  hallituksen  puolesta

För  Förbundsrepubliken  Tysklands  regering

Karl  BORCHARD 

Helmut STAHL

Por  el  Gobierno  de  la  República  Hele´nica

For  Den  Hellenske  Republiks  regering

Für  die  Regierung  der  Griechischen  Republik

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  ΕλληνØκη(cid:139) ς  ∆ηµ(cid:239)κρÆ(cid:244)(cid:221)Æς

For  the  Government  of  the  Hellenic  Republic

Pour  le  gouvernement  de  la  Re´publique  helle´nique

Per  il  governo  della  Repubblica  ellenica

Voor  de  regering  van  de  Helleense  Republiek

Pelo  Governo  da  República  Hele´nica

Helleenien  tasavallan  hallituksen  puolesta

För  Republiken  Greklands  regering

Emmanuel  FRAGOULIS

L  67/12

EN

Official  Journal  of  the  European  Communities

13.3.1999

Por  el  Gobierno  del  Reino  de  España

For  Kongeriget  Spaniens  regering

Für  die  Regierung  des  Königreichs  Spanien

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)(cid:239)υ  ΒÆ(cid:243)Øλ(cid:229)(cid:221)(cid:239)υ  (cid:244)ης  Ι(cid:243)(cid:240)Æν(cid:221)Æς

For  the  Government  of  the  Kingdom  of  Spain

Pour  le  gouvernement  du  Royaume  d’Espagne

Per  il  governo  del  Regno  di  Spagna

Voor  de  regering  van  het  Koninkrijk  Spanje

Pelo  Governo  do  Reino  de  Espanha

Espanjan  kuningaskunnan  hallituksen  puolesta

För  Konungariket  Spaniens  regering

ad  referendum
Antonio  Ortiz  GARCÍA

Por  el  Gobierno  de  Irlanda

For  Irlands  regering

Für  die  Regierung  Irlands

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  ΙρλÆν(cid:228)(cid:221)Æς

For  the  Government  of  Ireland

Pour  le  gouvernement  de  l’Irlande

Per  il  governo  dell’Irlanda

Voor  de  regering  van  Ierland

Pelo  Governo  da  Irlanda

Irlannin  hallituksen  puolesta

För  Irlands  regering

Thelma  M.  DORAN

13.3.1999

EN

Official  Journal  of  the  European  Communities

L  67/13

Por  el  Gobierno  de  la  República  Italiana

For  Den  Italienske  Republiks  regering

Für  die  Regierung  der  Italienischen  Republik

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  Ι(cid:244)ÆλØκη(cid:139) ς  ∆ηµ(cid:239)κρÆ(cid:244)(cid:221)Æς

For  the  Government  of  the  Italian  Republic

Pour  le  gouvernement  de  la  Re´publique  italienne

Per  il  governo  della  Repubblica  italiana

Voor  de  regering  van  de  Italiaanse  Republiek

Pelo  Governo  da  República  Italiana

Italian  tasavallan  hallituksen  puolesta

För  Republiken  Italiens  regering

Vincenzo  MANNO

Por  el  Gobierno  del  Gran  Ducado  de  Luxemburgo

For  Storhertugdømmet  Luxembourgs  regering

Für  die  Regierung  des  Großherzogtums  Luxemburg

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)(cid:239)υ  Μ(cid:229)γ(cid:192)λ(cid:239)υ  ∆(cid:239)υκ(cid:192)(cid:244)(cid:239)υ  (cid:244)(cid:239)υ  Λ(cid:239)υŒ(cid:229)µ(cid:226)(cid:239)υ(cid:139) ργ(cid:239)υ

For  the  Government  of  the  Grand  Duchy  of  Luxembourg

Pour  le  gouvernement  du  Grand-Duche´ de  Luxembourg

Per  il  governo  del  Granducato  di  Lussemburgo

Voor  de  regering  van  het  Groothertogdom  Luxemburg

Pelo  Governo  do  Grão-Ducado  do  Luxemburgo

Luxemburgin  suurherttuakunnan  hallituksen  puolesta

För  Storhertigdömet  Luxemburgs  regering

Georges  SANTER

L  67/14

EN

Official  Journal  of  the  European  Communities

13.3.1999

Por  el  Gobierno  del  Reino  de  los  Países  Bajos

For  Kongeriget  Nederlandenes  regering

Für  die  Regierung  des  Königreichs  der  Niederlande

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)(cid:239)υ  ΒÆ(cid:243)Øλ(cid:229)(cid:221)(cid:239)υ  (cid:244)ων  Κ(cid:192)(cid:244)ω  (cid:204)ωρω(cid:139) ν

For  the  Government  of  the  Kingdom  of  the  Netherlands

Pour  le  gouvernement  du  Royaume  des  Pays-Bas

Per  il  governo  del  Regno  dei  Paesi  Bassi

Voor  de  regering  van  het  Koninkrijk  der  Nederlanden

Pelo  Governo  do  Reino  dos  Países  Baixos

Alankomaiden  kuningaskunnan  hallituksen  puolesta

För  Konungariket  Nederländernas  regering

Hans  A.F.M.  FÖRSTER

Por  el  Gobierno  de  la  República  de  Austria

For  Republikken  Østrigs  regering

Für  die  Regierung  der  Republik  Österreich

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  ∆ηµ(cid:239)κρÆ(cid:244)(cid:221)Æς  (cid:244)ης  Αυ(cid:243)(cid:244)ρ(cid:221)Æς

For  the  Government  of  the  Republic  of  Austria

Pour  le  gouvernement  de  la  Re´publique  d’Autriche

Per  il  governo  della  Repubblica  d’Austria

Voor  de  regering  van  de  Republiek  Oostenrijk

Pelo  Governo  da  República  da  Áustria

Itävallan tasavallan hallituksen  puolesta

För  Republiken  Österrikes  regering

Irene  FREUDENSCHUSS-REICHL

13.3.1999

EN

Official  Journal  of  the  European  Communities

L  67/15

Por  el  Gobierno  de  la  República  Portuguesa

For  Den  Portugisiske  Republiks  regering

Für  die  Regierung  der  Portugiesischen  Republik

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  Π(cid:239)ρ(cid:244)(cid:239)γÆλØκη(cid:139) ς  ∆ηµ(cid:239)κρÆ(cid:244)(cid:221)Æς

For  the  Government  of  the  Portuguese  Republic

Pour  le  gouvernement  de  la  Re´publique  portugaise

Per  il  governo  della  Repubblica  portoghese

Voor  de  regering  van  de  Portugese  Republiek

Pelo  Governo  da  República  Portuguesa

Portugalin  tasavallan  hallituksen  puolesta

För  Republiken  Portugals  regering

Álvaro  Jose´ Costa  DE  MENDONÇA  E  MOURA

Por  el  Gobierno  de  la  República  de  Finlandia

For  Republikken  Finlands  regering

Für  die  Regierung  der  Republik  Finnland

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)ης  ΦØνλÆν(cid:228)Øκη(cid:139) ς  ∆ηµ(cid:239)κρÆ(cid:244)(cid:221)Æς

For  the  Government  of  the  Republic  of  Finland

Pour  le  gouvernement  de  la  Re´publique  de  Finlande

Per  il  governo  della  Repubblica  di  Finlandia

Voor  de  regering  van  de  Republiek  Finland

Pelo  Governo  da  República  da  Finlândia

Suomen  tasavallan  hallituksen  puolesta

För  Republiken  Finlands  regering

Eva-Christina MÄKELÄINEN

L  67/16

EN

Official  Journal  of  the  European  Communities

13.3.1999

Por  el  Gobierno  del  Reino  de  Suecia

For  Kongeriget  Sveriges  regering

Für  die  Regierung  des  Königreichs  Schweden

ΓØÆ  (cid:244)ην  κυ(cid:226)(cid:229)(cid:139) ρνη(cid:243)η  (cid:244)(cid:239)υ  ΒÆ(cid:243)Øλ(cid:229)(cid:221)(cid:239)υ  (cid:244)ης  Σ(cid:239)υη(cid:228)(cid:221)Æς

For  the  Government  of  the  Kingdom  of  Sweden

Pour  le  gouvernement  du  Royaume  de  Sue`de

Per  il  governo  del  Regno  di  Svezia

Voor  de  regering  van  het  Koninkrijk  Zweden

Pelo  Governo  do  Reino  da  Sue´cia

Ruotsin  kuningaskunnan  hallituksen  puolesta

För  Konungariket  Sveriges  regering

Björn  SKALA

Por  la  Comunidad  Europea  de  la  Energía  Atómica

For  Det  Europæiske  Atomenergifællesskab

Für  die  Europäische  Atomgemeinschaft

ΓØÆ  (cid:244)ην  Ευρω(cid:240)Æϊκη(cid:139) Κ(cid:239)Øν(cid:222)(cid:244)η(cid:244)Æ  Α(cid:244)(cid:239)µØκη(cid:139) ς  Εν(cid:229)(cid:139) ργ(cid:229)ØÆς

For  the  European  Atomic  Energy  Community

Pour  la  Communaute´ europe´enne  de  l’e´nergie  atomique

Per  la  Comunità  europea  dell’energia  atomica

Voor  de  Europese  Gemeenschap  voor  Atoomenergie

Pela  Comunidade  Europeia  da  Energia  Atómica

Euroopan  atomienergiayhteisön  puolesta

För  Europeiska  atomenergigemenskapen

Lars-Erik  LUNDIN

13.3.1999

EN

Official  Journal  of  the  European  Communities

L  67/17

Por  el  Organismo  Internacional  de  Energía  Atómica

For  Den  Internationale  Atomenergiorganisation

Für  die  Internationale  Atomenergie-Organisation

ΓØÆ  (cid:244)(cid:239)ν  ∆Ø(cid:229)θνη(cid:139) ˆργÆνØ(cid:243)µ(cid:222)  Α(cid:244)(cid:239)µØκη(cid:139) ς  Εν(cid:229)(cid:139) ργ(cid:229)ØÆς

For  the  International  Atomic  Energy  Agency

Pour  l’Agence  internationale  de  l’e´nergie  atomique

Per  l’Agenzia  internazionale  dell’energia  atomica

Voor  de  Internationale  Organisatie  voor  Atoomenergie

Pela  Ageˆncia  Internacional  da  Energia  Atómica

Kansainvälisen atomienergiajärjestön puolesta

För  Internationella  atomenergiorganet

Mohamed  ELBARADEI

L  67/18

EN

Official  Journal  of  the  European  Communities

13.3.1999

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  at  point  5.1.1(b)  of  Annex  II.

Gas  centrifuges  means  centrifuges  as  described  in  the  introductory  note  to  point  5.1  of  Annex  II.

(ii)  The  manufacture  of  diffusion  barriers.

Diffusion  barriers  means  thin,  porous  filters  as  described  in  point  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  point  5.7  of  Annex  II.

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

Electromagnetic  isotope  separators  means  those  items  referred  to  in  point  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 points 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  points  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  point  5.8.3  of  Annex  II.

(viii)  The  manufacture  of  zirconium  tubes.

Zirconium  tubes  means  tubes  as  described  in  point  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  1:5 000.

(x)  The  manufacture  of  nuclear  grade  graphite.

Nuclear  grade  graphite  means  graphite  having  a  purity  level  better  than  five  parts  per  million  boron
equivalent  and  with  a  density  greater  than  1,50  g/cm3.

(xi)  The  manufacture  of  flasks  for  irradiated  fuel.

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

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(xii)  The  manufacture  of  reactor  control  rods.

Reactor  control  rods  means  rods  as  described  in  point  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  points  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  point  3.1  of  Annex  II.

(xv)  The  construction  of  hot  cells.

Hot cells means a cell or interconnected cells totalling at least 6 m3  in volume with shielding equal to
or  greater  than  the  equivalent  of  0,5  m  of  concrete,  with  a  density  of  3,2  g/cm3  or  greater,  outfitted
with  equipment  for  remote  operations.

L  67/20

EN

Official  Journal  of  the  European  Communities

13.3.1999

ANNEX  II

List of specified equipment and non-nuclear material for the reporting of exports and imports according to
Article  2(a)(ix)

1. 

REACTORS  AND  EQUIPMENT  THEREFOR

1.1. 

Complete  nuclear  reactors

Nuclear reactors capable of operation so as to maintain a controlled 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’.

1.2. 

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 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.

1.3. 

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  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.

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1.4. 

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.

Explanatory  note

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

1.5. 

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  at  an  operating  pressure  in  excess  of  5,1  MPa  (740
psi).

1.6. 

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, and in which the relation of hafnium to zirconium is less than 1:500
parts  by  weight.

1.7. 

Primary  coolant  pumps

Pumps especially designed or prepared for circulating the primary coolant for nuclear reactors as
defined  in  paragraph  1.1.

Explanatory  note

Especially  designed  or  prepared  pumps  may  include  elaborate  sealed  or  multisealed  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

2.1. 

Deuterium  and  heavy  water

Deuterium,  heavy  water  (deuterium  oxide)  and  any  other  deuterium  compound  in  which  the
ratio  of  deuterium  to  hydrogen  atoms  exceeds  1:5000  for  use  in  a  nuclear  reactor  as  defined  in
paragraph  1.1  in  quantities  exceeding  200  kg  of  deuterium  atoms  for  any  one  recipient  country
in  any  period  of  12  months.

2.2. 

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/cm3  for  use  in  a  nuclear  reactor  as  defined  in  paragraph  1.1  in  quantities
exceeding  3  x  104  kg  (30  tonnes)  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.

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Official  Journal  of  the  European  Communities

13.3.1999

3. 

PLANTS  FOR  THE  REPROCESSING  OF 
EQUIPMENT  ESPECIALLY  DESIGNED  OR  PREPARED  THEREFOR

IRRADIATED  FUEL  ELEMENTS,  AND

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’ included the equipment and components
which normally come in direct contact with and directly control the irradiated fuel and the major
nuclear  material  and  fission  product  processing  streams.

These  processes,  including  the  complete  systems  for  plutonium  conversion  and  plutonium  metal
production,  may  be  identified  by  the  measures  taken  to  avoid  criticality  (e.g.  by  geometry),
radiation  exposure  (e.g.  by  shielding),  and  toxicity  hazards  (e.g.  by  containment).

Items of equipment that are considered to fall within the meaning of the phrase ‘and equipment
especially  designed  or  prepared’  for  the  reprocessing  of  irradiated  fuel  elements  include:

3.1. 

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.

3.2. 

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.

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3.3. 

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.

3.4. 

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  reused  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  2 %,  or

(2) a  maximum  diameter  of  175  mm  (7(cid:48))  for  cylindrical  vessels,  or

(3) a  maximum  width  of  75  mm  (3(cid:48))  for  either  a  slab  or  annular  vessel.

3.5. 

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
minimise  toxicity  hazards.

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3.6. 

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  minimise  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:

5.1. 

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 (3(cid:48)) and 400
mm (16(cid:48)) 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 minimise the imbalance. In contrast to other centrifuges, the gas
centrifuge for uranium enrichment is characterised by having within the rotor chamber a rotating
disc-shaped baffle(s) and a stationary tube arrangement for feeding and extracting to UF6  gas and
featuring  at  least  three  separate  channels,  of  which  two  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)  C o m p l e t e   r o t o r   a s s e m b l i e s

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

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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) R o t o r   t u b e s

Especially  designed  or  prepared  thin-walled  cylinders  with  thickness  of  12  mm  (0,5(cid:48))  or  less,  a
diameter of between 75 mm (3(cid:48)) and 400 mm (16(cid:48)), and manufactured from one or more of the
high  strength  to  density  ratio  materials  described  in  the  explanatory  note  to  this  section.

(c)  R i n g s   o r   b e l l o w s

Components especially designed or prepared to give localised 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(cid:48))
or  less,  a  diameter  of  between  75  mm  (3(cid:48))  and  400  m  (16(cid:48)),  having  a  convolute,  and
manufactured  from  one  of  the  high  strength  to  density  ratio  materials  described  in  the
explanatory  note  to  this  section.

(d) B a f f l e s

Disc-shaped components of between 75 mm (3(cid:48)) and 400 m (16(cid:48)) diameter especially designed or
prepared to be mounted inside the centrifuge rotor tube, in order to isolate the take-off chamber
from the main separation chamber and, in some cases, to assist the UF6  gas circulation within the
main  separation  chamber  of  the  rotor  tube,  and  manufactured  from  one  of  the  high  strength  to
density  ratio  materials  described  in  the  explanatory  note  to  this  section.

(e)  T o p   c a p s / b o t t o m   c a p s

Disc-shaped  components  of  between  75  mm  (3(cid:48))  and  400  (16(cid:48))  diameter  especially  designed  or
prepared to fit to the ends of the rotor tube, and so contain the UF6  within the rotor tube, and in
some  cases  to  support,  retain  or  contain  as  an  integrated  part  an  element  of  the  upper  bearing
(top  cap)  or  to  carry  the  rotating  elements  of  the  motor  and  lower  bearing  (bottom  cap),  and
manufactured  from  one  of  the  high  strength  to  density  ratio  materials  described  in  the
explanatory  note  to  this  section.

Explanatory  note

The  materials  used  for  centrifuge  rotating  components  are:

(a)  maraging  steel  capable  of  an  ultimate  tensile  strength  of  2,05  x  109  N/m2  (300 000  psi)  or

more,

(b) aluminium  alloys  capable  of  an  ultimate  tensile  strength  of  0,46  x  109  N/m2  (67 000  psi)  or

more,

(c)  filamentary  materials  suitable  for  use  in  composite  structures  and  having  a  specific  modulus
of  12,3  x  106  m  or  greater  and  a  specific  ultimate  tensile  strength  of  0,3  x  106  m  or  greater
(‘Specific  Modulus’  is  the  Young’s  Modulus  in  N/m2  divided  by  the  specific  weight  in  N/m3;
‘Specific  Ultimate  Tensile  Strength’  is  the  ultimate  tensile  strength  in  N/m2  divided  by  the
specific  weight  in  N/m3.

5.1.2. 

Static  components

(a)  M a g n e t i c   s u s p e n s i o n   b e a r i n g s

Especially  designed  or  prepared  bearing  assemblies  consisting  of  an  annular  magnet  suspended
within  a  housing  containing  a  damping  medium.  The  housing  will  be  manufactured  from  a
UF6-resistant  material  (see  explanatory  note  to  Section  5.2).  The  magnet  couples  with  a  pole
piece or a second magnet fitted to the top cap described in Section 5.1.1.(e). The magnet may be
ring-shaped  with  a  relation  between  outer  and  inner  diameter  smaller  or  equal  to  1,6:1.  The
magnet may be in a form having an initial permeability of 0,15 H/m (120 000  in  CGS  units)  or
more,  or  a  remanence  of  98,5 %  or  more,  or  an  energy  product  of  greater  than  80  kJ/m3  (107
gauss-oersteds). In addition to the usual material properties, it is a prerequisite that the deviation
of the magnetic axes from the geometrical axes is limited to very small tolerances (lower than 0,1
mm  or  0,004  in)  or  that  homogeneity  of  the  material  of  the  magnet  is  specially  called  for.

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(b) B e a r i n g s / d a m p e r s

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)  M o l e c u l a r   p u m p s

Especially designed or prepared cylinders having internally machined or extruded helical grooves
and  internally  machines  bores.  Typical  dimensions  are  as  follows:  75  mm  (3(cid:48))  to  400  mm  (16(cid:48))
internal diameter, 10 mm (0,4(cid:48)) 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(cid:48)) or more in
depth.

(d) M o t o r   s t a t o r s

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
600-2 000 Hz and a power range of 50-1 000 VA. The stators consist of multiphase windings on
a  laminated  low  loss  iron  core  comprised  of  thin  layers  typically  2,0  mm  (0,08(cid:48))  thick  or  less.

(e)  C e n t r i f u g e   h o u s i n g / r e c i p i e n t s

Components especially designed 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(cid:48))  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°  or  less.  The  housing  may  also  be  a  honeycomb  type  structure  to  accommodate
several rotor tubes. The housings are made of or protected by materials resistant to corrosion by
UF6.

(f)  S c o o p s

Especially designed or prepared tubes up to 12 mm (0,5(cid:48)) internal diameter for the extraction of
UF6  gas  from  within  the  rotor  tube  by  a  pilot  tube  action  (that  is,  with  an  aperture  facing  into
the circumferential gas flow within the rotor tube, for example by bending the end of a radially
disposed  tube)  and  capable  of  being  fixed  to  the  central  gas  extraction  system.  The  tubes  are
made  of  or  protected  by  materials  resistant  to  corrosion  by  UF6.

5.2. 

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  UF6  to the centrifuges, to link the individual centrifuges to each
other  to  form  cascades  (or  stages)  to  allow  for  progressively  higher  enrichments  and  to  extract
the ‘product’ and ‘tails’ UF6  from  the  centrifuges,  together  with  the  equipment  required  to  drive
the  centrifuges  or  to  control  the  plant.

Normally UF6  is evaporated from the solid using heated autoclaves and is distributed in gaseous
form to the centrifuges by way of cascade header pipework. The ‘product’ and ‘tails’ UF6  gaseous
streams flowing from the centrifuges are also passed by way of cascade header pipework to cold
traps  (operating  at  about  203  K  (−70  °C))  where  they  are  condensed  prior  to  onward  transfer
into  suitable  containers  for  transportation  or  storage.  Because  an  enrichment  plant  consists  of
many thousands of centrifuges arranged in cascades there are many kilometres 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.

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5.2.1. 

Feed  systems/product  and  tails  withdrawal  systems

Especially  designed  or  prepared  process  systems  including:

—  feed autoclaves (or stations), used for passing UF6  to the centrifuge cascades at up to 100 kPa

(15  psi)  and  at  a  rate  of  1  kg/h  or  more,

—  desublimers  (or  cold  traps)  used  to  remove  UF6  from  the  cascades  at  up  to  3  kPa  (0,5  psi)
pressure. The desublimers are capable of being chilled to 203 K (−70 °C) and heated to 343
K  (70  °C),

—  ‘product’  and  ‘tails’  stations  used  for  trapping  UF6  into  containers.

This plant, equipment and pipework is wholly made of or lined with UF6-resistant materials (see
explanatory  note  to  this  section)  and  is  fabricated  to  very  high  vacuum  and  cleanliness
standards.

5.2.2. 

Machine  header  piping  systems

Especially  designed  or  prepared  piping  systems  and  header  systems  for  handling  UF6  within  the
centrifuge  cascades.  The  piping  network  is  normally  of  the  ‘triple’  header  system  with  each
centrifuge  connected  to  each  of  the  headers.  There  is  thus  a  substantial  amount  of  repetition  in
its form. It is wholly made of UF6-resistant materials (see explanatory note to this section) and is
fabricated  to  very  high  vacuum  and  cleanliness  standards.

5.2.3. 

UF6  mass  spectrometers/ion  sources

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

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

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

3.  electron  bombardment  ionisation  sources;

4.  having  a  collector  system  suitable  for  isotopic  analysis.

5.2.4. 

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 subassemblies of such
frequency  changers  having  all  of  the  following  characteristics:

1.  a  multiphase  output  of  600  to  2 000  Hz;

2.  high  stability  (with  frequency  control  better  than  0,1 %);

3.  low  harmonic  distortion  (less  than  2 %),  and

4.  an  efficiency  of  greater  than  80 %.

Explanatory  note

The items listed above either come into direct contact with the UF6  process gas or directly control
the  centrifuges  and  the  passage  of  the  gas  from  centrifuge  to  centrifuge  and  cascade  to
cascade.

Materials  resistant  to  corrosion  by  UF6  include  stainless  steel,  aluminium,  aluminium  alloys,
nickel  or  alloys  containing  60 %  or  more  nickel.

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5.3. 

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

Introductory  note

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

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(cid:48)) or less, and for tubular forms, a diameter of 25 mm
(1(cid:48))  or  less,  made  of  metallic,  polymer  or  ceramic  materials  resistant  to  corrosion  by  UF6,
and

(b) especially  prepared  compounds  or  powders  for  the  manufacture  of  such  filters.  Such
compounds and powders include nickel or alloys containing 60 % or more nickel, aluminium
oxide,  or  UF6-resistant  fully  fluorinated  hydrocarbon  polymers  having  a  purity  of  99,9 %  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(cid:48))
in  diameter  and  greater  than  900  mm  (35(cid:48))  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(cid:48)) in diameter, for containing the gaseous diffusion barrier, made of or lined with
UF6-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  m3/min.  or  more  of  UF6  and  with  a  discharge
pressure  of  up  to  several  hundred  kPa  (100  psi),  designed  for  long-term  operation  in  the  UF6
environment  with  or  without  an  electrical  motor  of  appropriate  power,  as  well  as  separate
assemblies  of  such  compressors  and  gas  blowers.  These  compressors  and  gas  blowers  have  a
pressure  ratio  between  2:1  and  6:1  and  are  made  of,  or  lined  with,  materials  resistant  to  UF6.

5.3.4. 

Rotary  shaft  seals

Especially  designed  or  prepared  vacuum  seals,  with  seal  feed  and  seal  exhaust  connections,  for
sealing  the  shaft  connecting  the  compressor  or  the  gas  blower  rotor  with  the  driver  motor  so  as
to ensure a reliable seal against in-leaking of air into the inner chamber of the compressor or gas
blower which is filled with UF6. Such seals are normally designed for a buffer gas in-leakage rate
of  less  than  1 000  cm3/min  (60  in3/min).

5.3.5. 

Heat  exchangers  for  cooling  UF6

Especially  designed  or  prepared  heat  exchangers  made  of  or  lined  with  UF6-resistant  materials
(except  stainless  steel)  or  with  copper  or  any  combination  of  those  metals,  and  intended  for  a
leakage pressure change rate of less than 10 Pa (0,0015 psi) per hour under a pressure difference
of  100  kPa  (15  psi).

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5.4. 

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 UF6  to the gaseous diffusion assembly, to link the individual
assemblies  to  each  other  to  form  cascades  (or  stages)  to  allow  for  progressively  higher
enrichments  and  to  extract  the  ‘product’  and  ‘tails’  UF6  from  the  diffusion  cascades.  Because  of
the  high  inertial  properties  of  diffusion  cascades,  any  interruption  in  their  operation,  and
especially  their  shutdown,  leads  to  serious  consequences.  Therefore,  a  strict  and  constant
maintenance  of  vacuum  in  all  technological  systems,  automatic  protection  from  accidents,  and
precise  automated  regulation  of  the  gas  flow  is  of  importance  in  a  gaseous  diffusion  plant.  All
this leads to a need to equip the plant with a large number of special measuring, regulating and
controlling  systems.

Normally UF6  is evaporated from cylinders placed within autoclaves and is distributed in gaseous
form  to  the  entry  point  by  way  of  cascade  header  pipework.  The  ‘product’  and  ‘tails’  UF6
gaseous streams flowing from exit points are passed by way of cascade header pipework to either
cold traps or to compression stations where the UF6  gas is liquefied prior to onward transfer into
suitable  containers  for  transportation  or  storage.  Because  a  gaseous  diffusion  enrichment  plant
consists  of  a  large  number  of  gaseous  diffusion  assemblies  arranged  in  cascades,  there  are  many
kilometres  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  UF6  to  the  gaseous  diffusion  cascades,

—  desublimers  (or  cold  traps)  used  to  remove  UF6  from  diffusion  cascades,

—  liquefaction stations where UF6  gas from the cascade is compressed and cooled to form liquid

UF6,

—  ‘product’  or  ‘tails’  stations  used  for  transferring  UF6  into  containers.

5.4.2. 

Header  piping  systems

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

5.4.3. 

Vacuum  systems

(a)  Especially designed or prepared large vacuum manifolds, vacuum headers and vacuum pumps

having  a  suction  capacity  of  5  m3/min.  (175  ft3/min.)  or  more.

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

5.4.4. 

Special  shut-off  and  control  valves

Especially  designed  or  prepared  manual  or  automated  shut-off  and  control  bellows  valves  made
of UF6-resistant materials with a diameter of 40 to 1 500 mm (1,5 to 59(cid:48)) for installation in main
and  auxiliary  systems  of  gaseous  diffusion  enrichment  plants.

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5.4.5. 

UF6  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  UF6  gas  streams  and  having  all  of  the  following
characteristics:

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

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

3.  Electron  bombardment  ionisation  sources;

4.  collector  system  suitable  for  isotopic  analysis.

Explanatory  note

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

5.5. 

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

Introductory  note

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

Explanatory  note

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

5.5.1. 

Separation  nozzles

Especially designed or prepared separation nozzles and assemblies thereof. The separation nozzles
consist of slit-shaped, curved channels having a radius of curvature less than 1 mm (typically 0,1
to  0,05  mm),  resistant  to  corrosion  by  UF6  and  having  a  knife-edge  within  the  nozzle  that
separates  the  gas  flowing  through  the  nozzle  into  two  fractions.

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 UF6, having a
diameter of between 0,5 cm and 4 cm, a length to diameter ratio of 20:1 or less and with one or

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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  UF6  and  with  a  suction
volume  capacity  of  2  m3/min.  or  more  of  UF6/carrier  gas  (hydrogen  or  helium)  mixture.

Explanatory  note

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

5.5.4. 

Rotary  shaft  seals

Especially  designed  or  prepared  rotary  shaft  seals,  with  seal  feed  and  seal  exhaust  connections,
for  sealing  the  shaft  connecting  the  compressor  rotor  or  the  gas  blower  rotor  with  the  driver
motor so as to ensure a reliable seal against out-leakage of process gas or in-leakage of air or seal
gas into the inner chamber of the compressor or gas blower which is filled with a UF6/carrier gas
mixture.

5.5.5. 

Heat  exchangers  for  gas  cooling

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

5.5.6. 

Separation  element  housings

Especially  designed  or  prepared  separation  element  housings,  made  of  or  protected  by  materials
resistant  to  corrosion  by  UF6,  for  containing  vortex  tubes  or  separation  nozzles.

Explanatory  note

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

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  UF6, including:

(a)  feed  autoclaves,  ovens,  or  systems  used  for  passing  UF6  to  the  enrichment  process;

(b) desublimers  (or  cold  traps)  used  to  remove  UF6  from  the  enrichment  process  for  subsequent

transfer  upon  heating;

(c)  solidification  or  liquefaction  stations  used  to  remove  UF6  from  the  enrichment  process  by

compressing  and  converting  UF6  to  a  liquid  or  solid  form;

(d) ‘product’  or  ‘tails’  stations  used  for  transferring  UF6  into  containers.

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5.5.8. 

Header  piping  systems

Especially  designed  or  prepared  header  piping  systems,  made  of  or  protected  by  materials
resistant  to  corrosion  by  UF6  for  handling  UF6  within  the  aerodynamic  cascades.  This  piping
network  is  normally  of  the  ‘double’  header  design  with  each  stage  or  group  of  stages  connected
to  each  of  the  headers.

5.5.9. 

Vacuum  systems  and  pumps

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

(b) Vacuum  pumps  especially  designed  or  prepared  for  service  in  UF6-bearing  atmospheres  and
made  of  or  protected  by  materials  resistant  to  corrosion  by  UF6.  These  pumps  may  use
fluorocarbon  seals  and  special  working  fluids.

5.5.10. 

Special  shut-off  and  control  valves

Especially  designed  or  prepared  manual  or  automated  shut-off  and  control  bellows  valves  made
of or protected by materials resistant to corrosion by UF6  with a diameter of 40 to 1 500 mm for
installation  in  main  and  auxiliary  systems  of  aerodynamic  enrichment  plants.

5.5.11.  UF6  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  UF6  gas  streams  and  having  all  of  the
following characteristics:

1.  unit  resolution  for  mass  greater  than  320;

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

3.  electron  bombardment  ionisation  sources;

4.  collector  system  suitable  for  isotopic  analysis.

5.5.12.  UF6/carrier  gas  separation  systems

Especially  designed  or  prepared  systems  for  separating  UF6  from  carrier  gas  (hydrogen  or
helium).

Explanatory  note

These  systems  are  designed  to  reduce  the  UF6  content  in  the  carrier  gas  to  1  ppm  or  less  and
many  incorporate  equipment  such  as:

(a)  cryogenic  heat  exchangers  and  cryoseparators  capable  of  temperatures  of  −120  °c  or  less,

or

(b) cryogenic  refrigeration  units  capable  of  temperatures  of  −120  °C  or  less,  or

(c)  separation  nozzle  or  vortex  tube  units  for  the  separation  of  UF6  from  carrier  gas,  or

(d) UF6  cold  traps  capable  of  temperatures  of  −20  °C  or  less.

5.6. 

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.

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

the 

solid-liquid 

ion-exchange  process,  enrichment 

In 
is  accomplished  by  uranium
adsorption/desorption  on  a  special,  very  fast-acting,  ion-exchange  resin  or  adsorbent.  A  solution
of  uranium  in  hydrochloric  acid  and  other  chemical  agents  is  passed  through  cylindrical
enrichment columns containing packed beds of the adsorbent. For a continuous process, a reflux
system  is  necessary  to  release  the  uranium  from  the  adsorbent  back  into  the  liquid  flow  so  that
‘product’  and 
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.

‘tails’  can  be  collected.  This 

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  reoxidation  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 U4+
out of the organic stream, adjusting the acid concentration and feeding to the electrochemical
reduction  cells.

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Explanatory  note

These systems consist of solvent extraction equipment for stripping the U4+  from the organic
stream into an aqueous solution, evaporation and/or other equipment to accomplish solution
pH  adjustment  and  control,  and  pumps  or  other  transfer  devices  for  feeding  to  the
electrochemical  reduction  cells.  A  major  design  concern  is  to  avoid  contamination  of  the
aqueous  stream  with  certain  metal  ions.  Consequently,  for  those  parts  in  contact  with  the
process  stream,  the  system  is  constructed  of  equipment  made  of  or  protected  by  suitable
materials  (such  as  glass,  fluorocarbon  polymers,  polyphenyl  sulfate,  polyether  sulfone,  and
resin-impregnated graphite).

5.6.4. 

Feed  preparation  systems  (chemical  exchange)

Especially  designed  or  prepared  systems  for  producing  high-purity  uranium  chloride  feed
solutions  for  chemical  exchange  uranium  isotope  separation  plants.

Explanatory  note

These  systems  consist  of  dissolution,  solvent  extraction  and/or  ion  exchange  equipment  for
purification  and  electrolytic  cells  for  reducing  the  uranium  U6+  or  U4+  to  U3+.  These  systems
produce  uranium  chloride  solutions  having  only  a  few  parts  per  million  of  metallic  impurities
such  as  chromium,  iron,  vanadium,  molybdenum  and  other  bivalent  or  higher  multi-valent
cations.  Materials  of  construction  for  portions  of  the  systems  processing  high-purity  U3+  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  U3+  to  U4+  for  return  to  the  uranium
isotope  separation  cascade  in  the  chemical  exchange  enrichment  process.

Explanatory  note

These  systems  may  incorporate  equipment  such  as:

(a)  equipment  for  contacting  chlorine  and  oxygen  with  the  aqueous  effluent  from  the  isotope
separation  equipment  and  extracting  the  resultant  U4+  into  the  stripped  organic  stream
returning  from  the  product  end  of  the  cascade,

(b) equipment  that  separates  water  from  hydrochloric  acid  so  that  the  water  and  the
concentrated  hydrochloric  acid  may  be  reintroduced  to  the  process  at  the  proper  locations.

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  fibres.  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 enough so as not to degrade in the exchange columns. The resins/adsorbents
are  especially  designed  to  achieve  very  fast  uranium  isotope  exchange  kinetics  (exchange  rate
half-time of less than 10 seconds) and are capable of operating at a temperature in the range of
100  °C  to  200  °C.

5.6.7. 

Ion  exchange  columns  (ion  exchange)

Cylindrical  columns  greater  than  1 000  mm  in  diameter  for  containing  and  supporting  packed
beds  of  ion  exchange  resin/adsorbent,  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  °C  to  200  °C  and
pressures  above  0,7  MPa  (102  psia).

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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  oxidising  agent(s)  used  in  ion  exchange  uranium  enrichment
cascades.

Explanatory  note

The  ion  exchange  enrichment  process  may  use,  for  example,  trivalent  titanium  (Ti3+)  as  a
reducing  cation  in  which  case  the  reduction  system  would  regenerate  Ti3+  by  reducing  Ti4+.  The
process  may  use,  for  example,  trivalent  iron  (Fe3+)  as  an  oxidant  in  which  case  the  oxidation
system  would  regenerate  Fe3+  by  oxidising  Fe2+.

5.7. 

Expecially  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 vapour and those in which the process medium is the vapour
of  a  uranium  compound.  Common  nomenclature  for  such  processes  include:  first  category,
atomic  vapour  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  vapour  (for  selective  photo-ionisation)  or  devices  to  feed  the

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

5.7.1. 

Uranium  vaporisation  systems  (AVLIS)

Especially designed or prepared uranium vaporisation systems which contain high-power strip or
scanning  electron  beam  guns  with  a  delivered  power  on  the  target  of  more  than  2,5  kW/cm.

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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  and
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  vapour  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  vapour  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  UF6  and
carrier  gas  to  150  K  or  less  and  which  are  corrosion  resistant  to  UF6.

5.7.6. 

Uranium  pentafluoride  product  collectors  (MLIS)

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

5.7.7. 

UF6/carrier  gas  compressors  (MLIS)

Especially designed or prepared compressors for UF6/carrier gas mixtures, designed for long term
operation  in  a  UF6  environment.  The  components  of  these  compressors  that  come  into  contact
with  process  gas  are  made  of  or  protected  by  materials  resistant  to  corrosion  by  UF6.

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5.7.8. 

Rotary  shaft  seals  (MLIS)

Especially  designed  or  prepared  rotary  shaft  seals,  with  seal  feed  and  seal  exhaust  connections,
for  sealing  the  shaft  connecting  the  compressor  rotor  with  the  driver  motor  so  as  to  ensure  a
reliable  seal  against  out-leakage  of  process  gas  or  in-leakage  of  air  or  seal  gas  into  the  inner
chamber  of  the  compressor  which  is  filled  with  a  UF6/carrier  gas  mixture.

5.7.9. 

Fluorination  systems  (MLIS)

Especially  designed  or  prepared  systems  for  fluorinating  UF5  (solid)  to  UF6  (gas).

Explanatory  note

These  systems  are  designed  to  fluorinate  the  collected  UF5  powder  to  UF6  for  subsequent
collection  in  product  containers  or  for  transfer  as  feed  to  MLIS  units  for  additional  enrichment.
In  one  approach,  the  fluorination  reaction  may  be  accomplished  within  the  isotope  separation
system  to  react  and  recover  directly  off  the  ‘product’  collectors.  In  another  approach,  the  UF5
powder  may  be  removed/transferred  from  the  ‘product’  collectors  into  a  suitable  reaction  vessel
(e.g.,  fluidised-bed  reactor,  screw  reactor  or  flame  tower)  for  fluorination.  In  both  approaches,
equipment  for  storage  and  transfer  of  fluorine  (or  other  suitable  fluorinating  agents)  and  for
collection  and  transfer  of  UF6  are  used.

5.7.10.  UF6  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  UF6  gas  streams  and  having  all  of  the
following characteristics:

1.  unit  resolution  for  mass  greater  than  320;

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

3.  electron  bombardment  ionisation  sources;

4.  collector  system  suitable  for  isotopic  analysis.

5.7.11. 

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  UF6, including:

(a)  feed  autoclaves,  ovens,  or  systems  used  for  passing  UF6  to  the  enrichment  process;

(b) desublimers  (or  cold  traps)  used  to  remove  UF6  from  the  enrichment  process  for  subsequent

transfer  upon  heating;

(c)  solidification  or  liquefaction  stations  used  to  remove  UF6  from  the  enrichment  process  by

compressing  and  converting  UF6  to  a  liquid  or  solid  form;

(d) ‘product’  or  ‘tails’  stations  used  for  transferring  UF6  into  containers.

5.7.12.  UF6/carrier  gas  separation  systems  (MLIS)

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

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Explanatory  note

These  systems  may  incorporate  equipment  such  as:

(a)  cryogenic  heat  exchangers  or  cryoseparators  capable  of  temperatures  of  −120  °C  or  less,  or

(b) cryogenic  refrigeration  units  capable  of  temperatures  of  −120  °C  or  less,  or

(c)  UF6  cold  traps  capable  of  temperatures  of  −20  °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 vapour laser and
a dye laser. The laser system for MLIS usually consists of a CO2  or excimer laser and a multipass
optical cell with revolving mirrors at both ends. Lasers or laser systems for both processes require
a  spectrum  frequency  stabiliser  for  operation  over  extended  periods  of  time.

5.8. 

Especially designed or prepared systems, equipment and components for use in plasma separation
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 ionising uranium vapour, 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.

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

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)  i o n   s o u r c e s

Especially  designed  or  prepared  single  or  multiple  uranium  ion  sources  consisting  of  a  vapour
source, ioniser, 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) i o n   c o l l e c t o r s

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;

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(c)  v a c u u m   h o u s i n g s

Especially  designed  or  prepared  vacuum  housings  for  uranium  electromagnetic  separators,
constructed of suitable non-magnetic materials such as stainless steel and designed for operation
at  pressures  of  0,1  Pa  or  lower;

Explanatory  note

The housings are specially designed to contain the ion sources, collector plates and water-cooled
liners  and  have  provision  for  diffusion  pump  connections  and  opening  and  closure  for  removal
and  reinstallation  of  these  components.

(d) M a g n e t   p o l e   p i e c e s

Especially  designed  or  prepared  magnet  pole  pieces  having  a  diameter  greater  than  2  m  used  to
maintain a constant magnetic field within a 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  period  of
eight  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  an  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.

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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  utilising  either  the  water-hydrogen  sulphide  exchange  process  or  the  ammonia-hydrogen
exchange  process  include  the  following:

6.1. 

Water  —  hydrogen  sulphide  exchange  towers

Exchange towers fabricated from fine carbon steel (such as ASTM A516) with diameters of 6 m
(20(cid:57))  to  9  m  (39(cid:57)),  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  utilising  the  water-hydrogen  sulphide  exchange  process.

6.2. 

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 %  H2S)  especially  designed
or  prepared  for  heavy  water  production  utilising  the  water-hydrogen  sulphide  exchange  process.
These blowers or compressors have a throughput capacity greater than or equal to 56 m3/second
(120,000 SCFM) while operating at pressures greater than or equal to 1,8 MPa (260 psi) suction
and  have  seals  designed  for  wet  H2S service.

6.3. 

Ammonia-hydrogen  exchange  towers

Ammonia-hydrogen  exchange  towers  greater  than  or  equal  to  35  m  (114,3(cid:57)  in  height  with
diameters  of  1,5  m  (4,9(cid:57)  to  2,5  m  (8,2(cid:57))  capable  of  operating  at  pressures  greater  than  15  MPa
(2225  psi)  especially  designed  or  prepared  for  heavy  water  production  utilising  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.

6.4. 

Tower  internals  and  stage  pumps

Tower  internals  and  stage  pumps  especially  designed  or  prepared  for  towers  for  heavy  water
production  utilising  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.

6.5. 

Ammonia  crackers

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

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6.6. 

Infrared  absorption  analysers

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

6.7. 

Catalytic  burners

Catalytic  burners  for  the  conversion  of  enriched  deuterium  gas  into  heavy  water  especially
designed  or  prepared  for  heavy  water  production  utilising  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 UO3,
conversion  of  UO3  to  UO2,  conversion  of  uranium  oxides  to  UF4  or  UF6,  conversion  of  UF4  to
UF6, conversion of UF6  to  UF4, conversion of UF4  to uranium metal, and conversion of uranium
fluorides  to  UO2.  Many  of  the  key  equipment  items  for  uranium  conversion  plants  are  common
to  several  segments  of  the  chemical  process  industry.  For  example,  the  types  of  equipment
employed  in  these  processes  may  include:  furnaces,  rotary  kilns,  fluidised  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,  F2,  CIF3,  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.

7.1. 

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

Explanatory  note

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

7.2. 

Especially  designed  or  prepared  systems  for  the  conversion  of  UO3  to  UF6

Explanatory  note

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

7.3. 

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

Explanatory  note

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

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7.4. 

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

Explanatory  note

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

7.5. 

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

Explanatory  note

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

7.6. 

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

Explanatory  note

Conversion UF4  to U metal is performed by reduction with magnesium (large batches) or calcium
(small  batches).  The  reaction  is  carried  out  at  temperatures  above  the  melting  point  of  uranium
(1 130  °C).

7.7. 

Especially  designed  or  prepared  systems  for  the  conversion  of  UF6  to  UO2

Explanatory  note

Conversion  of  UF6  to  UO2  can  be  performed  by  one  of  three  processes.  In  the  first,  UF6  is
reduced  and  hydrolysed  to  UO2  using  hydrogen  and  steam.  In  the  second,  UF6  is  hydrolysed  by
solution  in  water,  ammonia  is  added  to  precipitate  ammonium  diuranate,  and  the  diuranate  is
reduced  to  UO2  with  hydrogen  at  820  °C.  In  the  third  process,  gaseous  UF6, CO2  and  NH3  are
combined in water, precipitating ammonium uranyl carbonate. The ammonium aranyl carbonate
is  combined  with  steam  and  hydrogen  at  500-600  °C  to  yield  UO2.

UF6  to  UO2  conversion  is  often  performed  as  the  first  stage  of  a  fuel  fabrication  plant.

7.8. 

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

Explanatory  note

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

L  67/44

EN

Official  Journal  of  the  European  Communities

13.3.1999

ANNEX  III

To  the  extent  that  the  measures  in  this  Protocol  involve  nuclear  material  declared  by  the  Community  and
without prejudice to Article 1 of this Protocol, the Agency and the Community shall cooperate to facilitate
implementation  of  those  measures  and  shall  avoid  unnecessary  duplication  of  activities.

The  Community  shall  provide  the  Agency  with  information  relating  to  transfers,  for  both  nuclear  and
non-nuclear purposes, from each State to another Member State of the Community and to such transfers to
each  State  from  another  Member  State  of  the  Community  that  corresponds  to  the  information  to  be
provided under Article 2 (a)(vi)(b) and under Article 2(a)(vi)(c) in relation to exports and imports of source
material  which  has  not  reached  the  composition  and  purity  suitable  for  fuel  fabrication  or  for  being
isotopically enriched.

Each State shall provide the Agency with information relating to transfers to or from another Member State
of  the  Community  that  corresponds  to  the  information  on  specified  equipment  and  non-nuclear  material
listed  in  Annex  II  of  this  Protocol  to  be  provided  under  Article  2(a)(ix)(a)  in  relation  to  exports  and,  on
specific  request  of  the  Agency,  under  Article  2(a)(ix)(b)  in  relation  to  imports.

With regard to the Community’s Joint Research Centre, the Community shall also implement the measures
which  this  Protocol  sets  out  for  States,  as  appropriate  in  close  collaboration  with  the  State  on  whose
territory  an  establishment  of  the  centre  is  located.

The  Liaison  Committee,  established  under  Article  25(a)  of  the  Protocol  referred  to  in  Article  26  of  the
Safeguards  Agreement,  will  be  extended  in  order  to  allow  for  participation  by  representatives  of  the  States
and  adjustment  to  the  new  circumstances  resulting  from  this  Protocol.

For  the  sole  purposes  of  the  implementation  of  this  Protocol,  and  without  prejudice  to  the  respective
competences  and  responsibilities  of  the  Community  and  its  Member  States,  each  State  which  decides  to
entrust to the Commission of the European Communities implementation of certain provisions which under
this Protocol are the responsibility of the States, shall so inform the other Parties to the Protocol through a
side letter. The Commission of the European Communities shall inform the other Parties to the Protocol of
its  acceptance  of  any  such  decisions.