98/106/CFSP: Council Decision of 26 January 1998 amending Decision 94/942/CFSP on the joint action adopted by the Council on the basis of Article J.3 of the Treaty on European Union concerning the control of exports of dual-use goods
Date: 1998-01-26
Institutions: Council of the European Union
Subjects: customs regulations, dual-use good, export monitoring, nuclear fuel, nuclear technology, technology transfer

6.2.98

EN

Official  Journal  of  the  European  Communities

L  32/1

(Acts  adopted  under  Title  V  of  the  Treaty  on  European  Union)

COUNCIL  DECISION

of  26  January  1998

amending  Decision  94/942/CFSP  on  the  joint  action  adopted  by  the  Council  on  the  basis  of
Article  J.3  of  the  Treaty  on  European  Union  concerning  the  control  of  exports  of  dual-use
goods

(98/106/CFSP)

THE  COUNCIL  OF  THE  EUROPEAN  UNION,

regime  for  the  control  of  exports  of  dual-use  goods (2),
shall  be  amended  in  accordance  with  the  Annex  hereto.

Having  regard  to  the  Treaty  on  European  Union,  and  in
particular  Article  J.3  thereof,

Having  regard  to  the  general  guidelines  given  by  the
European  Council  held  at  Lisbon  on  26  and  27  June
1992,

Article  2

This  Decision  shall  be  published  in  the  Official  Journal.

Having  regard  to  Decision  94/942/CFSP (1),

Article  3

Whereas  Annex  I  to  Decision  94/942/CFSP  should  be
updated  in  order  to  take  into  account  developments  in
the Nuclear Suppliers’ Group and the Missile Technology
Control  Regime,

This  Decision  shall  enter  into  force  on  the  day  of  its
publication.

It shall apply from the 30th day following the date of its
publication.

HAS  DECIDED  AS  FOLLOWS:

Article  1

Done  at  Brussels,  26  January  1998.

The  list  of  dual-use  goods  in  Annex  I  to  Decision
94/942/CFSP,  referred  to  in  Article  2  of  that  Decision
and  in  Article  3(1)  of  Council  Regulation  (EC)  No
3381/94  of  19  December  1994  setting  up  a  Community

For  the  Council

The  President

R.  COOK

(1)  OJ  L  367,  31.12.1994,  p.  8.  Decision  as  last  amended  by

Decision  97/633/CFSP  (OJ  L  266,  29.9.1997,  p.  1).

(2)  OJ  L  367,  31.12.1994,  p.  1.  Regulation  as  amended  by
Regulation  (EC)  No  837/95  (OJ  L  90,  21.4.1995,  p.  1).

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6.2.98

ANNEX

The  list  of  dual-use  goods  in  Annex  I  to  Decision  94/942/CFSP,  as  last  amended  by  Decision  97/633/CFSP,  shall  be  amended  as
follows:

(1) Under  the  headling  ‘acronyms  and  abbreviations  used  in  this  index’  the  following  acronyms  and  meanings  shall  be

inserted:

‘AVLIS 

Atomic  vapour  “laser”  istope  separation

CRISLA 

Chemical  reaction  by  isotope  selective  “laser”  activation

MLIS 

molecular  “laser”  isotope  separation’.

(2) The  nuclear  technology  note  shall  be  replaced  by  the  following:

‘NUCLEAR  TECHNOLOGY  NOTE  (NTN)
(To  be  read  in  conjunction  with  section  E  of  Category  0)

The “technology” directly associated with any goods controlled in Category 0 is controlled according to the provisions
of  Category  0.

“Technology”  for  the  “development”  ,  “production”  or  “use”  of  goods  under  control  remains  under  control  even
when  applicable  to  non-controlled  goods.

The  approval  of  goods  for  export  also  authorises  the  export  to  the  same  end-user  of  the  minimum  “technology”
required  for  the  installation,  operation,  maintenance  and  repair  of  the  goods.

Controls  on  “technology”  transfer  do  not  apply  to  information  “in  the  pubic  domain”  or  to  “basic  scientific
research”.

(3) Changes  to  definitions  of  terms

1.  The  definitions  for  the  following  terms  shall  be  replaced  as  follows:

‘“effective  gramme”  (0  1)  of  “special  fissile  material”  means:

a.  for  plutonium  isotopes  and  uranium-233,  the  isotope  weight  in  grammes;

b.  for  uranium  enriched  1  per  cent  or  greater  in  the  isotope  uranium-235,  the  element  weight  in  grammes

multiplied  by  the  square  of  its  enrichment  expressed  as  a  decimal  weight  fraction;

c.  for uranium enriched below 1 per cent in the isotope uranium-235, the element weight in grammes multiplied

by  0,0001.

“Special fissile material” (0) means plutonium-239, uranium-233, “uranium enriched in the isotopes 235 or 233”,
and  any  material  containing  the  foregoing.’

2.  The  following  definitions  of  terms  shall  be  inserted:

‘“Materials  resistant  to  corrosion  by  UF6”  (0)  may  be  copper,  stainless  steel,  aluminium,  aluminium  oxide,
aluminium  alloys,  nickel  or  alloy  containing  60  weight  per  cent  or  more  nickel  and  UF6-resistent  fluorinated
hydrocarbon  polymers,  as  appropriate  for  the  type  of  separation  process.’

3.  The  definition  of  the  term  ‘Boron  equivalent’  shall  be  deleted.

4.  The  definition  of  the  term  ‘Other  fissile  materials’  shall  be  deleted.

6.2.98

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Official  Journal  of  the  European  Communities

L  32/3

(4) Category  0  shall  be  replaced  by  the  following  text:

‘0A 

SYSTEMS,  EQUIPMENT  AND  COMPONENTS

0A001  “Nuclear  reactors”  and  specially  designed  or  prepared  equipment  and  components  therefor,  as  follows:

a.  “nuclear  reactors”  capable  of  operation  so  as  to  maintain  a  controlled  self-sustaining  fission  chain

reaction;

b.  metal vessels, or major shop-fabricated parts therefor, specially designed or prepared to contain the core

of  a  “nuclear  reactor”,  including  the  reactor  vessel  head  for  a  reactor  pressure  vessel;

c.  manipulative  equipment  specially  designed  or  prepared  for  inserting  or  removing  fuel  in  a  “nuclear

reactor”.

d.  control  rods  specially  designed  or  prepared  for  the  control  of  the  fission  process  in  a  “nuclear  reactor”,

support  or  suspension  structures  therefor,  rod  drive  mechanisms  and  rod  guide  tubes;

e.  pressure  tubes  specially  designed  or  prepared  to  contain  fuel  elements  and  the  primary  coolant  in  a

“nuclear  reactor”  at  an  operating  pressure  in  excess  of  5,1  MPa;

f.  zirconium metal and alloys in the form of tubes or assemblies of tubes in which the ratio of hafnium of
zirconium  is  less  than  1:500  parts  by  weight,  specially  designed  or  prepared  for  use  in  “nuclear
reactor”;

g.  coolant  pumps  specially  designed  or  prepared  for  circulating  the  primary  coolant  of  “nuclear

reactors”;

h.  “nuclear  reactor  internals”  specially  designed  or  prepared  for  use  in  a  “nuclear  reactor”,  including
support  columns  for  the  core,  fuel  channels,  thermal  shields,  baffles,  core  grid  plates,  and  diffuser
plates;

Note: 

In entry 0A001.h, “nuclear reactor internals” means any major structure within a reactor vessel
which  has  one  or  more  functions  such  as  supporting  the  core,  maintaining  fuel  alignment,
directing  primary  coolant  flow,  providing  radiation  shields  for  the  reactor  vessel,  and  guiding
in-core  instrumentations.

i.  heat  exchangers  (steam  generators)  specially  designed  or  prepared  for  use  in  the  primary  coolant  circuit

of  a  “nuclear  reactor”;

j.  neutron detection and measuring instruments specially designed or prepared for determining neutron flux

levels  within  the  core  of  a  “nuclear  reactor”.

0B 

TEST,  INSPECTION  AND  PRODUCTION  EQUIPMENT

0B001  Plant  for  the  separation  of  isotopes  of  “natural  uranium”,  “depleted  uranium”  and  “special  fissile

materials”,  and  specially  designed  or  prepared  equipment  and  components  therefor,  as  follows:

a.  plant specially designed for separating isotopes of “natural uranium”, “depleted uranium”, and “special

fissile  materials”,  as  follows:

1.  gas  centrifuge  separation  plant;

2.  gaseous  diffusion  separation  plant;

3.  aerodynamic  separation  plant;

4.  chemical  exchange  separation  plant;

L  32/4

EN

Official  Journal  of  the  European  Communities

6.2.98

5.  ion-exchange  separation  plant;

6.  atomic  vapour  “laser”  isotope  separation  (AVLIS)  plant;

7.  molecular  “laser”  isotope  separation  (MLIS)  plant;

8.  plasma  separation  plant;

9.  electro  magnetic  separation  plant;

b.  gas  centrifuges  and  assemblies  and  components,  specially  designed  or  prepared  for  gas  centrifuge

separation  process,  as  follows:

Note: 

In  0B001.b,  “high  strength-to-density  ratio  material”  means  any  of  the  following:

a.  maraging  steel  capable  of  an  ultimate  tensile  strength  of  2 050  MPa  more;

b.  aluminium  alloys  capable  of  an  ultimate  tensile  strength  of  460  MPa  or  more;  or

c.  “fibrous  or  filamentary  materials”  with  a  “specific  modulus”  of  more  than  3,18  ×  106  m

and  a  “specific  tensile  strength”  greater  than  76,2  ×  103  m;

1.  gas  centrifuges;

2. 

complete  rotor  assemblies;

3. 

4. 

rotor tube cylinders with a wall thickness of 12 mm or less, a diameter of between 75 mm and 400
mm,  made  from  “high  strength-to-density  ratio  matrials”;

rings or bellows with a wall thickness of 3 mm or less and a diameter of between 75 mm and 400
mm  and  designed  to  give  local  support  to  a  rotor  tube  or  to  join  a  number  together,  made  from
“high  strength-to-density  ratio  materials”;

5.  baffles of between 75 mm and 400 mm diameter for mounting inside a rotor tube, made from “high

strength-to-density  ratio  materials”.

6. 

top or bottom caps of between 75 mm and 400 mm diameter to fit the ends of a rotor tube, made
from  “high  strength-to-density  ratio  materials”;

7.  magnetic suspension bearings consisting of an annular magnet suspended within a housing made of
or protected by “materials resistant to corrosion by UF6” containing a damping medium and having
the  magnet  coupling  with  a  pole  piece  or  second  magnet  fitted  to  the  top  cap  of  the  rotor;

8. 

specially  prepared  bearings  comprising  a  pivot-cup  assembly  mounted  on  a  damper;

9.  molecular pumps comprised of cylinders having internally machined or extruded helical grooves and

internally  machined  bores;

10.  ring-shaped  motor  stators  for  multiphase  AC  hysteresis  (or  reluctance)  motors  for  synchronous
operation within a vacuum in the frequency range of 600 to 2 000 Hz and a power range of 50 to
1 000  Volt-Amps;

11.  centrifuge  housing/recipients  to  contain  the  rotor  tube  assembly  of  a  gas  centrifuge,  consisting  of  a
rigid cylinder of wall thickness up to 30 mm with precision machined ends and made of or protected
by  “materials  resistant  to  corrosion  by  UF6”;

12.  scoops  consisting  of  tubes  of  up  to  12  mm  internal  diameter  for  the  extraction  of  UF6  gas  from
within a centrifuge rotor tube by a Pitot tube action, made of or protected by “materials resistant to
corrosion  by  UF6”;

6.2.98

EN

Official  Journal  of  the  European  Communities

L  32/5

13.  frequency  changers  (converters  or  inverters)  specially  designed  or  prepared  to  supply  motor  stators
for  gas  centrifuge  enrichment,  having  all  of  the  following  characteristics,  and  specially  designed
components  therefor:

a.  multiphase  output  of  600  to  2 000  Hz;

b.  frequency  control  better  than  0,1 %;

c.  harmonic  distortion  of  less  than  2 %;  and

d.  an  efficiency  greater  than  80 %;

c.  equipment  and  components,  specially  designed  or  prepared  for  gaseous  diffusion  separation  process,  as

follows:

1.  gaseous  diffusion  barriers  made  of  porous  metallic,  polymer  or  ceramic  “materials  resistant  to
corrosion  by  UF6”  with  a  pore  size  of  10  to  100  nm,  a  thickness  of  5  mm  or  less,  and,  for  tubular
forms,  a  diameter  of  25  mm  or  less;

2.  gaseous  diffuser  housings  made  of  or  protected  by  “materials  resistant  to  corrosion  by  UF6”;

3.  compressors  (positive  displacement,  centrifugal  and  axial  flow  types)  or  gas  blowers  with  a  suction
volume  capacity  of  1  m3/min  or  more  of  UF6,  and  discharge  pressure  up  to  666,7  kPa,  made  of  or
protected  by  “materials  resistant  to  corrosion  by  UF6”;

4.  rotary  shaft  seals  for  compressors  or  blowers  specified  in  0B001.c.3.  and  designed  for  a  buffer  gas

in-leakage  rate  of  less  than  1 000  cm3/min.;

5.  heat  exchangers  made  of  aluminium,  copper,  nickel,  or  alloys  containing  more  than  60  per  cent
nickel, or combinations of these metals as clad tubes, designed to operate at sub-atmospheric pressure
with a leak rate that limits the pressure rise to less than 10 Pa per hour under a pressure differential
of  100  kPa;

6.  bellow valves made of or protected by “materials resistant to corrosion by UF6”, with a diamater of

40  mm  to  1 500  mm;

d.  equipment  and  components,  specially  designed  or  prepared  for  aerodynamic  separation  process,  as

follows:

1.  separation nozzles consisting of slit-shaped, curved channels having a radius of curvature less than 1
mm,  resistant  to  corrosion  by  UF6,  and  having  a  knife-edge  contained  within  the  nozzle  which
separates  the  gas  flowing  through  the  nozzle  into  two  streams;

2.  tangential  inlet  flow-driven  cylindrical  or  conical  tubes  (vortex  tubes),  made  of  or  protected  by
“materials resistant to corrosion by UF6”, with a diameter of between 0,5 cm and 4 cm and a length
to  diameter  ratio  of  20:1  or  less  and  with  one  or  more  tangential  inlets;

3.  compressors  (positive  displacement,  centrifugal  and  axial  flow  types)  or  gas  blowers  with  a  suction
volume capacity of 2 m3/min, made of or protected by “materials resistant to corrosion by UF6”, and
rotary  shaft  seals  therefor;

4.  heat  exchangers  made  of  or  protected  by  “materials  resistant  to  corrosion  by  UF6”;

5.  aerodynamic  separation  element  housings,  made  of  or  protected  by  “materials  resistant  to  corrosion

by  UF6”  to  contain  vortex  tubes  or  separation  nozzles;

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6.2.98

6.  bellows valves made of or protected by “materials resistant to corrosion by UF6”, with a diameter of

40  to  1 500  mm;

7.  process  systems  for  separating  UF6  from  carrier  gas  (hydrogen  or  helium)  to  1  ppm  UF6  content  or

less, inlcuding:

a.  cryogenic  heat  exchangers  and  cryoseparators  capable  of  temperatures  of  153  K  (−120 °C)  or

less;

b.  cryogenic  refrigeration  units  capable  of  temperatures  of  153  K  (−120 °C)  or  less;

c.  separation  nozzle  or  vortex  tube  units  for  the  separation  of  UF6  from  carrier  gas;

d.  UF6  cold  traps  capable  of  temperatures  of  253  K  (−20 °C)  or  less;

e. equipment and components, specially designed or prepared for chemical exchange separation process, as

follows:

1.  fast-exchange liquid-liquid pulse columns with stage residence time of 30 seconds or less and resistant
to  concentrated  hydrochloric  acid  (e. g.  made  of  or  protected  by  suitable  plastic  materials  such  as
fluorocarbon  polymers  or  glass);

2.  fast-exchange liquid-liquid centrifugal contactors with stage residence time of 30 seconds or less and
resistant  to  concentrated  hydrochloric  acid  (e.g.  made  of  or  protected  by  suitable  plastic  materials
such  as  fluorocarbon  polymers  or  glass);

3.  electrochemical  reduction  cells  resistant  to  concentrated  hydrochloric  acid  solutions,  for  reduction  of

uranium  from  one  valence  state  to  another;

4.  electrochemical  reduction  cells  feed  equipment  to  take  U+4  from  the  organic  stream  and,  for  those
parts  in  contact  with  the  process  stream,  made  of  or  protected  by  suitable  materials  (e.g.  glass,
fluorocarbon  polymers,  polyphenyl  sulphate,  polyether  sulfone  and  resin-impregnated  graphite);

5.  feed  preparation  systems  for  producing  high  purity  uranium  chloride  solution  consisting  of
dissolution,  solvent  extraction  and/or  ion  exchange  equipment  for  purification  and  electrolytic  cells
for  reducing  the  uranium  U+6  or  U+4  to  U+3;

6.  uranium  oxidation  systems  for  oxidation  of  U+3  to  U+4;

f.  equipment  and  components,  specially  designed  or  prepared  for  ion-exchange  separation  process,  as

follows:

1.  fast  reacting  ion-exchange  resins,  pellicular  or  porous  macro-reticulated  resins  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,  with
diameters  of  0,2  mm  or  less,  resistant  to  concentrated  hydrochloric  acid  and  designed  to  have  an
exchange rate half-time of less than 10 seconds and capable of operating at temperatures in the range
of  373  K  (100 °C)  to  473  K  (200 °C);

2.  ion exchange columns (cylindrical) with a diameter greater than 1 000 mm, made of or protected by
materials  resistant  to  concentrated  hydrochloric  acid  (e.g.  titanium  or  fluorocarbon  plastics)  and
capable of operating at temperatures in the range of 373 K (100 °C) to 473 K (200 °C) and pressures
above  0,7  MPa;

3.  ion  exchange  reflux  systems  (chemical  or  electrochemical  oxidation  or  reduction  systems)  for
regeneration  of  the  chemical  reducing  or  oxidising  agents  used  in  ion  exchange  enrichment
cascades;

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g.  equipment and components, specially designed or prepared for atomic vapour “laser” isotope separation

process  (AVLIS),  as  follows:

1.  high power strip or scanning electron beam guns with a delivered power of more than 2,5 kW/cm for

use  in  uranium  vaporisation  systems;

2.  liquid uranium metal handling systems for molten uranium or uranium alloys, consisting of crucibles,
made  of  or  protected  by  suitable  corrosion  and  heat  resistant  materials  (e.g.  tantalum,  yttria-coated
graphite,  graphite  coated  with  other  rare  earth  oxides  or  mixtures  thereof),  and  cooling  equipment
for  the  crucibles;

NB:  SEE  ALSO  2A225

3.  product and tails collector systems made of or lined with materials resistant to the heat and corrosion

of  uranium  metal  vapour  or  liquid,  such  as  yttria-coated  graphite  or  tantalum;

4.  separator  module  housings  (cylindrical  or  rectangular  vessels)  for  containing  the  uranium  metal

vapour  source,  the  electron  beam  gun  and  the  product  and  tails  collectors;

5.  “lasers”  or  “laser”  systems  for  the  separation  of  uranium  isotopes  with  a  spectrum  frequency

stabiliser  for  operation  over  extended  periods  of  time;

NB:  SEE  ALSO  6A005  AND  6A205

h.  equipment  and  components,  specially  designed  or  prepared  for  molecular  “laser”  isotope  separation

process  (MLIS)  or  chemical  reaction  by  isotope  selective  laser  activation  (CRISLA),  as  follows:

1.  supersonic expansion nozzles for cooling mixtures of UF6  and carrier gas to 150 K (−123 °C) or less

and  made  from  “materials  resistant  to  corrosion  by  UF6”;

2.  uranium pentafluoride (UF5), product collectors consisting of filter, impact or cyclone-type collectors

or  combinations  thereof,  and  made  of  “materials  resistant  to  corrosion  by  UF5/UF6”;

3.  compressors made of or protected by “materials resistant to corrosion by UF6, and rotary shaft seals

therefor;

4.  equipment  for  fluorinating  UF5  (solid)  to  UF6  (gas);

5.  process  systems  for  separating  UF6  from  carrier  gas  (e. g.  nitrogen  or  argon)  including:

a.  cryogenic  heat  exchangers  and  cryoseparators  capable  of  temperatures  153  K  (−120 °C)  or  less;

b.  cryogenic  refrigeration  units  capable  of  temperatures  of  153  K  (−120 °C)  or  less;

c.  UF6  cold  traps  capable  of  temperatures  of  253  K  (−20 °C)  or  less;

6.  “lasers”  or  “laser”  systems  for  the  separation  of  uranium  isotopes  with  a  spectrum  frequency

stabiliser  for  operation  over  extended  periods  of  time;

NB:  SEE  ALSO  6A005  AND  6A205

i.  equipment  and  components,  specially  designed  or  prepared  for  plasma  separation  process,  as  follows:

1.  microwave power sources and antennae for producing or accelerating ions, with an output frequency

greater  than  30  GHz  and  mean  power  output  greater  than  50  kW;

2.  radio  frequency  ion  excitation  coils  for  frequencies  of  more  than  100  kHz  and  capable  of  handling

more  than  40  kW  mean  power;

3.  uranium  plasma  generation  systems;

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4.  liquid metal handling systems for molten uranium or uranium alloys, consisting of crucibles, made of
or  protected  by  suitable  corrosion  and  heat  resistant  materials  (e.g.  tantalum,  yttria-coated  graphite,
graphite  coated  with  other  rare  earth  oxides  or  mixtures  thereof),  and  cooling  equipment  for  the
crucibles;

NB:  SEE  ALSO  2A225

5.  product  and  tails  collectors  made  of  or  protected  by  materials  resistant  to  the  heat  and  corrosion  of

uranium  vapour  such  as  yttria-coated  graphite  or  tantalum;

6.  separator  module  housings  (cylindrical)  for  containing  the  uranium  plasma  source,  radio-frequency
drive  coil  and  the  product  and  tails  collectors  and  made  of  a  suitable  non-magnetic  material  (e.g.
stainless  steel);

j.  equipment  and  components,  specially  designed  or  prepared  for  electromagnetic  separation  process,  as

follows:

1.  ion sources, single  or multiple,  consisting of a vapour source, ioniser, and beam accelerator made of
suitable  non-magnetic  materials  (e.g.  graphite,  stainless  steel,  or  copper)  and  capable  of  providing  a
total  ion  beam  current  of  50  mA  or  greater;

2.  ion  collector  plates  for  collection  of  enriched  or  depleted  uranium  ion  beams,  consisting  of  two  or
more  slits  and  pockets  and  made  of  suitable  non-magnetic  materials  (e.g.  graphite  or  stainless
steel);

3.  vacuum  housings  for  uranium  electromagnetic  separators  made  of  non-magnetic  materials  (e.g.

stainless  steel)  and  designed  to  operate  at  pressures  of  0,1  Pa  or  lower;

4.  magnet  pole  pieces  with  a  diameter  greater  than  2  m;

5.  high  voltage  power  supplies  for  ion  sources,  having  all  of  the  following  characteristics:

a.  capable  of  continuous  operation;

b.  output  voltage  of  20 000  V  or  greater;

c.  output  current  of  1  A  or  greater;  and

d.  voltage  regulation  of  better  than  0,01 %  over  a  period  of  8  hours;

NB:  SEE  ALSO  3A227

6.  magnet  power  supplies  (high  power,  direct  current)  having  all  of  the  following  characteristics:

a.  capable of continuous operation with a current output of 500 A or greater at a voltage of 100 V

or  greater;  and

b.  current  or  voltage  regulation  better  than  0,01 %  over  a  period  of  8  hours.

NB:  SEE  ALSO  3A  226

0B002 

Specially  designed  or  prepared  auxiliary  systems,  equipment  and  components,  as  follows,  for  isotope
separation  plant  specified  in  0B001,  made  of  or  protected  by  “materials  resistant  to  corrosion  by  UF6”:

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.  product  and  tails  stations  for  transferring  UF6  into  containers;

d.  liquefaction  or  solidification  stations  used  to  remove  UF6  from  the  enrichment  process  by  compressing,

cooling  and  converting  UF6  to  a  liquid  or  solid  form;

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e.  piping  systems  and  header  systems  specially  designed  for  handling  UF6  within  gaseous  diffusion,

centrifuge  or  aerodynamic  cascades;

f.  1.  vacuum  manifolds  or  vacuum  headers  having  a  suction  capacity  of  5  m3/minute  or  more;  or

2.  vacuum  pumps  specially  designed  for  use  in  UF6  bearing  atmospheres;

g.  UF6  mass  spectrometers/ion  sources  specially  designed  or  prepared  for  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  of  more  than  320  amu;

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

3.  electron  bombardment  ionisation  sources;  and

4.  collector  system  suitable  for  isotopic  analysis.

0B003  Plant  for  the  conversion  of  uranium  and  equipment  specially  designed  or  prepared  therefor,  as  follows:

a.  systems  for  the  conversion  of  uranium  ore  concentrates  to  UO3;

b.  systems  for  the  conversion  of  UO3  to  UF6;

c.  systems  for  the  conversion  of  UO3  to  UO2;

d.  systems  for  the  conversion  of  UO2  to  UF4;

e.  systems  for  the  conversion  of  UF4  to  UF6;

f.  systems  for  the  conversion  of  UF4  to  uranium  metal;

g.  systems  for  the  conversion  of  UF6  to  UO2;

h.  systems  for  the  conversion  of  UF6  to  UF4;

0B004  Plant for the production or concentration of heavy water, deuterium and deuterium compounds and specially

designed  or  prepared  equipment  and  components  therefor,  as  follows:

a.  plant  for  the  production  of  heavy  water,  deuterium  or  deuterium  compounds,  as  follows:

1.  water-hydrogen  sulphide  exchange  plants;

2.  ammonia-hydrogen  exchange  plants;

b.  equipment  and  components,  as  follows:

1.  water-hydrogen  sulphide  exchange  towers  fabricated  from  fine  carbon  steel  (e.g.  ASTM  A516)  with
diameters of 6 m to 9 m, capable of operating at pressures greater than or equal to 2 MPa and with a
corrosion  allowance  of  6  mm  or  greater;

2.  single  stage,  low  head  (i.e.  0,2  MPa)  centrifugal  blowers  or  compressors  for  hydrogen  sulphide  gas
circulation (i.e. gas containing more than 70 % H2S) with a throughput capacity greater than or equal
to  56  m3/second  when  operating  at  pressures  greater  than  or  equal  to  1,8  MPa  suction  and  having
seals  designed  for  wet  H2  service;

3.  ammonia-hydrogen exchange towers greater than or equal to 35 m in height with diameters of 1,5 m

to  2,5  m  capable  of  operating  at  pressures  greater  than  15  MPa;

4.  tower  internals,  including  stage  contactors,  and  stage  pumps,  including  those  which  are  submersible,

for  heavy  water  production  utilizing  the  ammonia-hydrogen  exchange  process;

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5.  ammonia  crackers  with  operating  pressures  greater  than  or  equal  to  3  MPa  for  heavy  water

production  utilising  the  ammonia-hydrogen  exchange  process;

6.  infrared  absorption  analysers  capable  of  on-line  hydrogen/deuterium  ratio  analysis  where  deuterium

concentrations  are  equal  to  or  greater  than  90 %;

7.  catalytic  burners  for  the  conversion  of  enriched  deuterium  gas  into  heavy  water  utilising  the

ammonia-hydrogen  exchange  process;

8.  complete  heavy  water  upgrade  systems,  or  columns  therefor,  for  the  upgrade  of  heavy  water  to

reactor-grade  deuterium  concentration.

0B005  Plant  specially  designed  for  the  fabrication  of  “nuclear  reactor”  fuel  elements  and  specially  designed  or

prepared  equipment  therefor.

Note: 

A  plant  for  the  fabrication  of  “nuclear  reactor”  fuel  elements  includes  equipment  which:

a.  normally comes into direct contact with or directly processes or controls the production flow of

nuclear materials;

b.  seals  the  nuclear  materials  within  the  cladding;

c.  checks  the  integrity  of  the  cladding  or  the  seal;  or

d.  checks  the  finish  treatment  of  the  solid  fuel.

0B006  Plant  for  the  reprocessing  of  irradiated  “nuclear  reactor”  fuel  elements,  and  specially  designed  or  prepared

equipment  and  components  therefor.

Note: 

0B006  includes:

a.  plant for the reprocessing of irradiated “nuclear reactor” fuel elements including equipment and
components  which  normally  come  into  direct  contact  with  and  directly  control  the  irradiated
fuel  and  the  major  nuclear  material  and  fission  product  processing  streams;

b.  fuel  element  chopping  or  shredding  machines,  i.e.  remotely  operated  equipment  to  cut,  chop,

shred  or  shear  irradiated  “nuclear  reactor”  fuel  assemblies,  bundles  or  rods;

c.  dissolvers, critically safe tanks (e.g. small diameter, annular or slab tanks) specially designed or
prepared  for  the  dissolution  of  irradiated  “nuclear  reactor”  fuel,  which  are  capable  of
withstanding  hot,  highly  corrosive 
loaded  and
maintained;

liquids,  and  which  can  be  remotely 

d.  counter-current solvent extractors and ion-exchange processing equipment specially designed or
prepared  for  use  in  a  plant  for  the  reprocessing  of  irradiated  “natural  uranium”,  “depleted
uranium”  or  “special  fissile  materials”;

e.  holding  or  storage  vessels  specially  designed  to  be  critically  safe  and  resistant  to  the  corrosive

effects  of  nitric  acid;

Note: 

holding  or  storage  vessels  may  have  the  following  features:

1.  walls  or  intenal  structures  with  a  boron  equivalent  (calculated  for  all  constituent

elements  as  defined  in  the  note  to  0C004)  of  at  least  two %;

2.  a  maximum  diameter  or  175  mm  for  cylindrical  vessels;  or

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

f.  complete  systems  specially  designed  or  prepared  for  the  conversion  of  plutonium  nitrate  to

plutonium  oxide;

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g.  complete  systems  specially  designed  or  prepared  for  the  production  of  plutonium  metal;

h.  process control instrumentation specially designed or prepared for monitoring or controlling the
irradiated  “natural  uranium”,  “depleted  uranium”  or  “special  fissile

reprocessing  of 
materials”.

0C 

MATERIALS

0C001  “Natural  uranium”  or  “depleted  uranium”  or  thorium  in  the  form  of  metal,  alloy,  chemical  compound  or

concentrate  and  any  other  material  containing  one  or  more  of  the  foregoing;

Note: 

0C001  does  not  control  the  following:

a.  four grammes or less of “natural uranium” or “depleted uranium” when contained in a sensing

component  in  insruments;

b.  “depleted  uranium”  specially  fabricated  for  the  following  civil  non-nuclear  applications:

1.  shielding;

2.  packaging;

3.  ballasts  having  a  mass  not  greater  than  100  kg;

4.  counter-weights  having  a  mass  not  greater  than  100  kg;

c.  alloys  containing  less  than  5 %  thorium;

d.  ceramic  products  containing  thorium,  which  have  been  manufactured  for  non-nuclear  use.

0C002  “Special fissile materials”.

Note: 

0C002  does  not  control  four  “effective  grammes”  or  less  when  contained  in  a  sensing  component
in  instruments.

0C003  Deuterium,  heavy  water  (deuterium  oxide)  and  other  compounds  of  deuterium,  and  mixtures  and  solutions

containing  deuterium,  in  which  the  isotopic  ratio  of  deuterium  to  hydrogen  exceeds  1:5 000.

0C004  Graphite, nuclear grade, having a purity level of less than 5 parts per million “boron equivalent” and with a

density  greater  than  1,5  g/cm3.

Note: 

In  0C004,  ‘boron  equivalent’  (BE)  is  defined  as  the  sum  of  BEZ  for  impurities  (excluding  BEcarbon
since  carbon  is  not  considered  an  impurity)  including  boron,  where:

BEZ  (ppm)  =  CF  ×  concentration  of  element  Z  in  ppm;

where  CF  is  the  conversion  factor =

(cid:243)ZAB
(cid:243)BAZ

and  (cid:243)B  and  (cid:243)Z  are  the  thermal  neutron  capture  cross  sections,  (in  barns)  for  naturally  occurring
boron  and  element  Z  respectively;  and  AB  and  AZ  are  the  atomic  masses  of  naturally  occurring
boron  and  element  Z  respecively.

0C005  Specially  prepared  compounds  or  powders  for  the  manufacture  of  gaseous  diffusion  barriers,  resistant  to
corrosion  by  UF6  (e.g.  nickel  or  alloy  containing  60  weight  per  cent  or  more  nickel,  aluminium  oxide  and
fully  fluorinated  hydrocarbon  polymers),  having  a  purity  of  99.9  weight  per  cent  or  more  and  a  mean
particle  size  of  less  than  10  micrometres  measured  by  American  Society  for  Testing  and  Materials  (ASTM)
B330  standard  and  a  high  degree  of  particle  size  uniformity.

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0D 

SOFTWARE

0D001  “Software” specially designed or modified for the “development”, “production” or “use” of goods specified

in  this  category.

0E 

TECHNOLOGY

0E001  “Technology” according to the Nuclear Technology Note for the “development”, “production” or “use” of

goods  specified  in  this  category.’

(5) After  sub-entry  1C111.c.5  the  following  sub-entry  shall  be  inserted:

‘6.  Ferrocene  derivatives  other  than  those  specified  in  the  Military  Goods  Controls.’

(6) Entry  6A107  shall  be  replaced  as  follows:

‘6A107  Gravity  meters  (gravimeters)  and  components  for  gravity  meters  and  gravity  gradiometers,  as  follows:

a.  Gravity meters, other than those specified in 6A007.b, designed or modified for airborne or marine use,
and having a static or operational accuracy of 0,7 mgal or less (better), and having a time-to-steady-state
registration  of  two  minutes  or  less;

b.  Specially  designed  components  for  gravity  meters  specified  in  6A007.b  or  6A107.a  and  gravity

gradiometers  specified  in  6A007.c’