WO2000031747A1 - Method and installation for treating a nuclear fuel powder - Google Patents
Method and installation for treating a nuclear fuel powder Download PDFInfo
- Publication number
- WO2000031747A1 WO2000031747A1 PCT/FR1999/002834 FR9902834W WO0031747A1 WO 2000031747 A1 WO2000031747 A1 WO 2000031747A1 FR 9902834 W FR9902834 W FR 9902834W WO 0031747 A1 WO0031747 A1 WO 0031747A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- particles
- size
- powder
- reduction
- reduced
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B02—CRUSHING, PULVERISING, OR DISINTEGRATING; PREPARATORY TREATMENT OF GRAIN FOR MILLING
- B02C—CRUSHING, PULVERISING, OR DISINTEGRATING IN GENERAL; MILLING GRAIN
- B02C18/00—Disintegrating by knives or other cutting or tearing members which chop material into fragments
- B02C18/06—Disintegrating by knives or other cutting or tearing members which chop material into fragments with rotating knives
- B02C18/062—Disintegrating by knives or other cutting or tearing members which chop material into fragments with rotating knives with rotor elements extending axially in close radial proximity of a concentrically arranged slotted or perforated ring
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
- Y02P10/00—Technologies related to metal processing
- Y02P10/20—Recycling
Definitions
- the present invention relates to a method and an installation for treating a nuclear fuel powder.
- the invention relates more particularly to the treatment of such a powder, of the oxide type, such as U0 2 , obtained downstream of the step aimed at transforming into this oxide a compound, such as UFg.
- the powder having undergone this conversion step is then subjected to a phase of reduction of the average size of the particles which constitute it.
- U0 2 can be obtained in different ways.
- a first mode leads to the production of coarse aggregates, the average diameter of which is around 1 mm.
- the step of reducing the average size of the particles consists in shifting the particle size spectrum as a whole, without modifying the general appearance of this spectrum. This is obtained, in the usual way, by grinding by means of mechanical installations, such as for example ball, hammer or air jet mills. All of the particles forming the combustible powder are subjected to the action of these mechanical mills.
- the average size of the particles flowing through this sieve is therefore less than that of the particles admitted upstream of the latter. Contrary to the techniques aiming to shift the granulometric spectrum as a whole, one proceeds here to a clipping, which contributes to modify the general shape of this spectrum.
- the particles of large size, retained by the mesh of the sieve, must be subjected to operations aimed at recycling and defluorinating them with a view to their subsequent mixing with finer particles.
- Damaged screens can be repaired to keep costs down, but these repairs reduce the filtering surface.
- the use of sieves induces a clogging problem, due to the fact that the powder agglomerates and clogs the sieve. It is then necessary to implement unclogging, for example by ultrasound, or even by percussion, which then causes mechanical degradation of the screen.
- the present invention proposes to implement a method for treating nuclear fuel powder making it possible to overcome all of the drawbacks inherent in the various methods of the prior art mentioned above.
- the invention also relates to an installation for treating a powder of a nuclear combustible material, of the type containing an oxide, such as U0 2 , said installation being arranged in particular downstream of a unit for converting said oxide into a compound, such as UF s , said installation comprising a unit for reducing the average size of the particles forming the powder, inducing a modification in the general appearance of the spectrum of particles, said unit comprising so-called particle retaining means coarse, larger than a predetermined size, or critical size, said retaining means being capable of allowing free flow of so-called fine particles, of size smaller than the critical size, characterized in that said reduction unit also comprises means for continuously reducing coarse particles, so as to form particles, called reduced, of size smaller than the critical size, as well as means for distributing the reduced particles in the free flow of fine particles.
- the invention makes it possible to achieve the objectives mentioned above. Indeed, the fact of reducing the particles whose size is greater than a critical size, in order to disperse them among the particles flowing freely allows, while not allowing the passage of a precise fraction of the powder, to get rid of the operation of evacuation of this fraction considered, as was the case in the prior art using sieves.
- the process according to the invention therefore proves to be significantly less contaminating than those using such sieves.
- the process according to the invention is also capable of operating continuously, without appreciable flow break and possibly by means of successive powders of different natures. It also allows the treatment of powders whose flow rates are able to vary significantly.
- the process according to the invention has remarkable efficiency, in so far as all the particles flowing downstream of the reduction means actually have a size less than the predetermined critical size.
- the process according to the invention guarantees, to a large extent, an absence of pollution, since it does not involve either re-treatment of products which may have been eliminated, or reprocessing of any fluids used to reduce the particle size.
- the nuclear fuel powder processing installation according to the invention is very flexible. Indeed, it is likely to treat products whose enrichment, even the nature, are different. Since the installation according to the invention is devoid of zone of retention of powder, it is not necessary to carry out any cleaning when switching from one product to another.
- the installation according to the invention makes it possible to reach high flow rates, which can for example be five to ten times greater than those authorized by means of a treatment installation using screens.
- the installation of the invention generates reduced operating costs compared to the prior art. It also guarantees a very satisfactory integrity of the treated powder, since it makes it possible to avoid, to a large extent, all overheating and therefore does not induce any oxidation phenomenon. Since this installation does not use any lubricant, the powder, during its passage through the installation, is not subject to contamination due to its contact with such an external product.
- the installation according to the invention overcomes clogging problems, thanks to the drive effect of the turbine which equips it and which causes a suction of the powder during its passage through the unit. particle reduction.
- the installation according to the invention is also very flexible in terms of adjustments since the critical size, above which particles are reduced, can be modulated very simply by modifying one of the parameters of the installation involved in determining this critical size. In addition, once this critical size has been determined, no further adjustment is necessary.
- FIG. 1 is a schematic view of a nuclear fuel powder processing installation according to the invention
- - Figure 2 is an exploded perspective view, with parts broken away, of the various constituent elements of the particle reduction unit of the installation of Figure 1
- - Figure 3 is a partial diametral sectional view of the reduction unit of Figure 2;
- FIG. 4 is a cross section from above, showing a turbine and cutting blades belonging to the particle reduction unit illustrated in FIGS. 2 and 3.
- FIG. 1 shows, schematically, a nuclear fuel powder processing installation.
- This installation is provided, at its upper end, or upstream, with a flange or crown 2 allowing the docking of a container 4 whose bottom is provided with a valve not shown, for example of the guillotine type.
- This container is loaded with a nuclear fuel powder obtained by conversion, for example in a dry process, intended to transform an initial compound such as UF 6 into an oxide, such as U0 2 .
- the crown 2 surmounts a pipe 6 extending, at its lower end, by a conical hopper 8 with a double envelope.
- Line 6 is provided, at its upper end, with a detection probe 12 suitable for detecting the presence of powder and being in relation to an automatic valve 14 intended to close the line in the absence of powder.
- a flow regulator not shown, is provided at the downstream end of the pipe 6, at the connection with the hopper 8.
- This hopper 8 is connected, at its downstream end, to a metal particle detector of known type, designated in as a whole by the reference 18.
- This detector which is provided with a bypass line 20 capable of collecting metallic impurities, is connected, via an intermediate tube 22, to a unit 24 for reducing powder particles.
- This reduction unit 24 which will be described in more detail below, is connected, at its downstream end, to an outlet conduit 26 of the installation, in which the treated nuclear fuel powder circulates, which is directed towards a storage unit 27.
- This outlet duct 26 is provided with a valve 28 intended to selectively block the flow thereof.
- a double pipe 29 (or recirculation) makes it possible to balance the pressure between upstream and downstream of the unit 24 for reducing powder particles.
- Figures 2 and 3 illustrate the particle reduction unit 24, shown on a larger scale than in Figure 1.
- This unit 24 comprises a hopper 30 for admitting powder to be treated, placed in communication with the downstream end of the tube 22 shown in FIG. 1.
- This hopper 30 is provided, at its lower end, with a collar 32 which is flush, as shown in particular in Figure 3, the upstream end of a chamber 34, in which are housed all the elements arranged downstream of the flange 32.
- the latter is supported, by means of a annular flange 36, against the upper end of a micro-cutting head designated as a whole by the reference 38.
- this micro-cutting head 38 comprises two annular flanges respectively upper 40 and lower 42, between which blades are arranged 44.
- the upper flange 40 bears against the underside of the flange 32 and against a shoulder 46 which is provided with an upper edge 48 of the chamber 34.
- the lower flange 42 is secured, for example by screwing, to a support 50, the lower end of which rests on a non-chassis depicted of the installation.
- the annular head 38 receives, in its internal volume, a circular turbine 52, comprising two flanges respectively upper 54 and lower 56, between which fins 58 are fixed, which will be shown more precisely in FIG. 4.
- the upper flange 54 has a frustoconical upper end 60 defining an upstream orifice 62 of the turbine 52, placed in communication with the downstream end of the inlet funnel 30.
- the lower flange 56 has a bottom 64 extended by an upper flange 66.
- This bottom 64 is pierced with a central orifice intended for the passage of a stud 68, cooperating with a washer 70 and a nut 72 for the purpose of fixing the turbine 52 to a shaft 74 for driving the turbine, which is connected to a motor not shown and is free to rotate inside the support 50.
- a connecting piece 75 surrounded by an O-ring 75A, is interposed between the bottom 64 and the shaft 74. This part 75 is fixed to the bottom by pins 75B.
- a lower retaining ring 76, or wear ring, to which a flange 78 of corresponding profile is attached, with the interposition of a seal of rectangular section 80, is disposed between the walls opposite the lower flange 42 of the head 38 and from the bottom 64 of the lower flange 56 of the turbine 52.
- FIG. 4 illustrates, on a larger scale than FIGS. 2 and 3, part of the blades 44 equipping the micro-cutting head 38, as well as one of the fins 58 equipping the turbine 52.
- the blades 44 are for example provided at number of 180, at the periphery of the micro-cutting head 38.
- Each blade 44 has, in top view, a generally rectangular profile and has two faces 82, 84 in relief, extending symmetrically with respect to the main axis A of this blade.
- the cross section of the blade increases towards the inside of the cutting head.
- These faces 82, 84 have draft angles a, a ', with respect to the axis A, which are between 0 and 10 °. These angles. and ⁇ 'can be the same or different.
- the distance d separating two adjacent blades 44, at their flared inner end, is for example between 0.03 and 3 mm and, preferably, between 0.1 and 0.4 mm.
- the axis A of each blade is inclined, relative to the diameter D of the cutting head, at an angle ⁇ between 0 and 10 °, preferably between 1 and 5 °. This inclination can be adjusted in a known manner.
- the fin 58 which extends over the outer periphery of the turbine 52, has a curved shape and comprises a body 58A made for example of stainless steel and terminated by an end plate 58B made of tungsten carbide.
- the opposite faces of the inner end of the blades 44 and of the plate 58B of the fin 58 are separated from a distance of between 0.3 and 0.6 mm, depending on the wear of the blades and the turbine.
- each fin 58 is rotated, according to arrow F, at a speed of between 6,000 and 12,000 revolutions per minute.
- the container 4 is approached on the crown 2.
- the container 4 valve, the valve 28 and a valve (not shown) controlling the supply of the nozzle 25 with nitrogen are successively opened.
- the particle detector 18 is started up and the upper automatic valve 14 is opened, so that the powder flows from the container 4 towards the reduction unit 24.
- the powder is admitted into the reduction unit 24 via the hopper 30, then flows towards the upstream orifice 62 of the turbine. It then pours onto the upper surface of the lower flange 56 of the turbine, and is driven centrifugally due to the high speed rotation to which this turbine is subjected. These particles are therefore directed towards the blades 44 with which the micro-cutting head 38 is provided.
- Two neighboring blades define, by their opposite lateral faces, a path 86 along which a particle larger than a particle which cannot be progressed cannot be advanced, which is also known as critical size.
- Each pair of adjacent blades 44 therefore constitutes a means for retaining coarse particles.
- the critical size is a function of the distance d separating the facing faces of two adjacent blades, the angles of inclination ⁇ and ′ of these faces, the angle of inclination ⁇ of each blade with respect to the diametrical axis D of the head 38, as well as of the speed of rotation of the turbine 52. Only the powder particles whose size is less than this critical size flow freely through the path 86 defined by the assembly of the blades 44.
- free flow means a flow in which the particles are not affected by the action of the blades 44.
- particles whose size is greater than this critical size are subjected to reduction by grinding. The latter is generated by the action of the end plates 58B of the fins 58, which, during their rotational movement, continuously shear the coarse particles against the active faces of the blades 44.
- the particles reduced to a size less than the critical size then flow along the paths provided by each pair of adjacent blades and are dispersed in the flow of particles of size below the critical size, which are not subjected to the 'action of the blades 44.
- the set of paths 86 the width of which increases towards the outside of the head 38, due to the clearance of the blades 44, forms a common path for the fine particles and the reduced particles.
- the particles initially admitted inside the turbine 52 flow, possibly after being reduced, towards the outside of the cutting head 38 and are admitted into the chamber 34.
- the average particle size, downstream of the blades 44, is less than that of the particles upstream of these blades, due to the grinding operation to which some of these particles are subjected.
- the reduction unit 24 therefore constitutes a unit for lowering the average size of the particles, inducing a modification of the general allule of the spectrum of these particles.
- the flow of the particles is directed by gravity towards the outlet conduit 26, so as to be stored in a container, not shown.
- the upper valve 14 is closed and an additional container, similar to that shown in FIG. 1, can be docked at the level of the upper crown 2.
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Life Sciences & Earth Sciences (AREA)
- Plasma & Fusion (AREA)
- Manufacturing & Machinery (AREA)
- Geology (AREA)
- Organic Chemistry (AREA)
- Food Science & Technology (AREA)
- Ceramic Engineering (AREA)
- Mechanical Engineering (AREA)
- Materials Engineering (AREA)
- Metallurgy (AREA)
- Environmental & Geological Engineering (AREA)
- Crushing And Pulverization Processes (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Compounds Of Alkaline-Earth Elements, Aluminum Or Rare-Earth Metals (AREA)
- Powder Metallurgy (AREA)
- Disintegrating Or Milling (AREA)
Abstract
Description
Claims
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR1020017006208A KR20010086039A (en) | 1998-11-19 | 1999-11-18 | Method and installation for treating a nuclear fuel powder |
JP2000584486A JP2002538413A (en) | 1998-11-19 | 1999-11-18 | Method and equipment for processing nuclear fuel powder |
EP99956080A EP1138045A1 (en) | 1998-11-19 | 1999-11-18 | Method and installation for treating a nuclear fuel powder |
AU12770/00A AU1277000A (en) | 1998-11-19 | 1999-11-18 | Method and installation for treating a nuclear fuel powder |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9814733A FR2786116B1 (en) | 1998-11-19 | 1998-11-19 | PROCESS AND PLANT FOR THE TREATMENT OF NUCLEAR FUEL POWDER |
FR98/14733 | 1998-11-19 |
Publications (1)
Publication Number | Publication Date |
---|---|
WO2000031747A1 true WO2000031747A1 (en) | 2000-06-02 |
Family
ID=9533077
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
PCT/FR1999/002834 WO2000031747A1 (en) | 1998-11-19 | 1999-11-18 | Method and installation for treating a nuclear fuel powder |
Country Status (9)
Country | Link |
---|---|
EP (1) | EP1138045A1 (en) |
JP (1) | JP2002538413A (en) |
KR (1) | KR20010086039A (en) |
CN (1) | CN1331829A (en) |
AR (1) | AR021280A1 (en) |
AU (1) | AU1277000A (en) |
FR (1) | FR2786116B1 (en) |
TW (1) | TW436809B (en) |
WO (1) | WO2000031747A1 (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR100969942B1 (en) * | 2008-12-26 | 2010-07-14 | 한전원자력연료 주식회사 | Crusher of raw materials |
Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3819804A (en) * | 1971-06-16 | 1974-06-25 | Gen Electric | Conversion of uranium hexafluoride to uranium dioxide structures of controlled density and grain size |
GB1468696A (en) * | 1973-09-05 | 1977-03-30 | Kernforschungsanlage Juelich | Comminution of nuclear fuel and/or breeder elements especially in recycling |
US4167081A (en) * | 1977-07-07 | 1979-09-11 | Westinghouse Electric Corp. | Centerless grinder |
US4439402A (en) * | 1980-12-16 | 1984-03-27 | Tokyo Shibaura Denki Kabushiki Kaisha | Nuclear fuel conversion systems |
EP0150737A2 (en) * | 1984-01-26 | 1985-08-07 | Westinghouse Electric Corporation | Process for treating nuclear fuel scrap |
US4582268A (en) * | 1982-08-12 | 1986-04-15 | Alkem Gmbh | Apparatus for treating a granular substance, especially nuclear reactor fuel in powder form, and method for operating the apparatus |
US4621775A (en) * | 1980-10-16 | 1986-11-11 | Jan Abom | High-speed mill for grinding biomass and like material |
US4676935A (en) * | 1980-03-19 | 1987-06-30 | Alkem Gmbh | Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid |
FR2622343A1 (en) * | 1987-10-26 | 1989-04-28 | Commissariat Energie Atomique | Process for the manufacture of nuclear fuel pellets based on mixed oxide (U,Pu)O2 |
US5405094A (en) * | 1994-01-31 | 1995-04-11 | Poser; Kimberly | Multi-staged size reduction machine |
FR2720540A3 (en) * | 1995-06-15 | 1995-12-01 | Siemens Ag | Compressed bodies of mixed oxide of uranium and plutonium |
US5607062A (en) * | 1995-08-18 | 1997-03-04 | Quadro Engineering Inc. | Screen module for preparing cosmetics nested screens of different mesh sizes |
-
1998
- 1998-11-19 FR FR9814733A patent/FR2786116B1/en not_active Expired - Fee Related
-
1999
- 1999-11-16 AR ARP990105808 patent/AR021280A1/en unknown
- 1999-11-18 KR KR1020017006208A patent/KR20010086039A/en not_active Application Discontinuation
- 1999-11-18 JP JP2000584486A patent/JP2002538413A/en active Pending
- 1999-11-18 AU AU12770/00A patent/AU1277000A/en not_active Abandoned
- 1999-11-18 WO PCT/FR1999/002834 patent/WO2000031747A1/en not_active Application Discontinuation
- 1999-11-18 EP EP99956080A patent/EP1138045A1/en not_active Withdrawn
- 1999-11-18 CN CN99814752A patent/CN1331829A/en active Pending
- 1999-11-19 TW TW88120210A patent/TW436809B/en not_active IP Right Cessation
Patent Citations (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3819804A (en) * | 1971-06-16 | 1974-06-25 | Gen Electric | Conversion of uranium hexafluoride to uranium dioxide structures of controlled density and grain size |
GB1468696A (en) * | 1973-09-05 | 1977-03-30 | Kernforschungsanlage Juelich | Comminution of nuclear fuel and/or breeder elements especially in recycling |
US4167081A (en) * | 1977-07-07 | 1979-09-11 | Westinghouse Electric Corp. | Centerless grinder |
US4676935A (en) * | 1980-03-19 | 1987-06-30 | Alkem Gmbh | Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid |
US4621775A (en) * | 1980-10-16 | 1986-11-11 | Jan Abom | High-speed mill for grinding biomass and like material |
US4439402A (en) * | 1980-12-16 | 1984-03-27 | Tokyo Shibaura Denki Kabushiki Kaisha | Nuclear fuel conversion systems |
US4582268A (en) * | 1982-08-12 | 1986-04-15 | Alkem Gmbh | Apparatus for treating a granular substance, especially nuclear reactor fuel in powder form, and method for operating the apparatus |
EP0150737A2 (en) * | 1984-01-26 | 1985-08-07 | Westinghouse Electric Corporation | Process for treating nuclear fuel scrap |
FR2622343A1 (en) * | 1987-10-26 | 1989-04-28 | Commissariat Energie Atomique | Process for the manufacture of nuclear fuel pellets based on mixed oxide (U,Pu)O2 |
US5405094A (en) * | 1994-01-31 | 1995-04-11 | Poser; Kimberly | Multi-staged size reduction machine |
FR2720540A3 (en) * | 1995-06-15 | 1995-12-01 | Siemens Ag | Compressed bodies of mixed oxide of uranium and plutonium |
US5607062A (en) * | 1995-08-18 | 1997-03-04 | Quadro Engineering Inc. | Screen module for preparing cosmetics nested screens of different mesh sizes |
Also Published As
Publication number | Publication date |
---|---|
CN1331829A (en) | 2002-01-16 |
FR2786116B1 (en) | 2001-01-12 |
JP2002538413A (en) | 2002-11-12 |
KR20010086039A (en) | 2001-09-07 |
TW436809B (en) | 2001-05-28 |
EP1138045A1 (en) | 2001-10-04 |
FR2786116A1 (en) | 2000-05-26 |
AU1277000A (en) | 2000-06-13 |
AR021280A1 (en) | 2002-07-03 |
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