EP1060476A1 - Method and installation for decontaminating metallic surfaces - Google Patents
Method and installation for decontaminating metallic surfacesInfo
- Publication number
- EP1060476A1 EP1060476A1 EP99903548A EP99903548A EP1060476A1 EP 1060476 A1 EP1060476 A1 EP 1060476A1 EP 99903548 A EP99903548 A EP 99903548A EP 99903548 A EP99903548 A EP 99903548A EP 1060476 A1 EP1060476 A1 EP 1060476A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- decontamination
- tank
- solution
- contactor
- cerium
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
- G21F9/002—Decontamination of the surface of objects with chemical or electrochemical processes
- G21F9/004—Decontamination of the surface of objects with chemical or electrochemical processes of metallic surfaces
Definitions
- the present invention relates to a method for decontaminating metal surfaces, according to which the latter are treated using an acid solution of cerium at valence 4, the ceric ion being regenerated with ozone.
- the metal surfaces to be decontaminated may or may not be covered with a layer of oxides. Decontamination takes place by reaction of the cerium acid with the metal and / or the oxide layer covering the surface of this metal.
- the metal surfaces in question can be contaminated with both natural and artificial radioisotopes as well as with non-radioactive elements.
- the surfaces are part of metal parts which can come from nuclear reactors of different types, such as pressurized water reactors, boiling water reactors, gas-cooled reactors or others.
- Radioactive contamination is either linked to the activation of impurities by the reactor core and the deposition and fixation of this contamination on the metal walls, or caused by radioactive leaks at the fuel elements and the deposition of fission products and fuel on the metal walls.
- Parts contaminated with radioactive materials can also come from manufacturing facilities. - 2 -
- nuclear fuels nuclear fuels, irradiated fuel reprocessing facilities, nuclear waste conditioning facilities, low, medium and high activity laboratories handling radioactive elements, radioactive waste storage facilities, and any facility in which radioactive products are manipulated.
- the metal parts contaminated with non-radioactive elements can be contaminated either by the deposition, or by the fixing of a contaminant on the metal or in the oxide layer present on the surface of the metal.
- the metals may have undergone oxidation at a temperature higher than room temperature, the layer of corrosion products formed having the particularity of strongly fixing the contaminating products.
- a decontamination process of the above kind used for decontamination of metal surfaces of parts or equipment from pressurized water nuclear reactors, and in particular the decontamination of chromium oxide from a chromium-nickel-iron alloy, is described in WO-A-85/04279.
- This known method comprises the treatment of surfaces contaminated with an aqueous oxidizing agent having a pH below 7 and containing cerium nitrate, chromic acid and ozone, at a temperature below 60 ° C and preferably less than 25 ° C.
- Oxidation is carried out at low temperature in the presence
- the oxidizing agent is an acidic solution of Ce saturated with ozone. This solution is sent cocurrently in the system to be decontaminated until total exhaustion in Ce 4 + / 0-, before returning to the ozonization reactor and finding its oxidizing potential "
- the object of the invention is to remedy these drawbacks and to provide a rapid and effective method for decontaminating metal surfaces.
- the metal surface is treated, that is to say oxidized, at a temperature between 60 ° C and 90 ° C with an acid solution of cerium containing cerium at valence 4 cerium being regenerated continuously at approximately the same temperature as that of the above-mentioned solution, said regeneration being carried out by injecting ozone into the decontamination solution in a gas-liquid contactor of the static mixer type in which the ozone and the acid solution based on cerium are transported in co-current. It has been found that through in-situ regeneration which
- US-A-4,162,229 discloses the treatment of surfaces contaminated with an aqueous solution based on a cerium salt (4) at a temperature between 20 ° C and 90 ° C followed by the removal of the solution and washing, while US-A-4,657,596 discloses the treatment of such surfaces with an aqueous solution containing ceric acid at temperatures between 70 ° C and 200 ° C. None of these documents describes a regeneration of cerium, which suggests that such a possible regeneration takes place in a separate step and at another temperature.
- the invention also relates to a device particularly intended for carrying out the method according to the above invention.
- the installation shown in the figure essentially comprises a decontamination tank 1 filled with decontamination solution, a gas-liquid regeneration contactor 2 connected to an ozone production system 3, and a buffer tank 4, the decontamination tank 1 , the contactor 2 and the buffer tank 4 being mounted - 5 -
- the decontamination tank 1 is made of zirconium and has for example a content of approximately 2 m 3. It is closed by a cover 6 on which ultrasonic probes 7 are fixed.
- This decontamination tank 1 is provided at its upper part with an overflow 8 connected to an evacuation duct 9 opening into the buffer tank 4 located below the decontamination tank 1 and heated by a heating system 10.
- this heating system 10 is not mounted in the buffer tank 4 but in the decontamination tank 1.
- the tank 1 has an exhaust pipe 11 for the gases opening into a gas treatment device 12 comprising in series a condenser 13, a diverter 14 and a unit for destroying residual ozone 15.
- the condensate of the condenser 13 is collected in a tank 16 and returned by the conduit 17 to the above-mentioned discharge conduit 9.
- a basket 18 for the parts to be decontaminated. Like the rest of the installation, it must be made of a material having a high corrosion resistance, although it may be weaker than the resistance of the material of the tank 1.
- This basket 18 and the other components such as the buffer tank 4, loop 5 and contactor 2 can - 6 -
- the circulation loop 5 comprises, apart from the discharge conduit 9, also a suction conduit 19 connected on the one hand to the bottom of the buffer tank 4 and on the other hand to a pump 20 and a discharge conduit 21 between the pump 20 and the bottom of the decontamination tank 1, the gas-liquid contactor 2 being mounted in this conduit 21.
- a duct 22 comprising a valve 23 connects this discharge duct 21, just below the decontamination tank 1 with the buffer tank 4.
- the ozone production system 3 is connected to the discharge pipe 21, between the pump 20 and the contactor 2, by a pipe 24.
- This ozone production system 3 comprises an ozonator 25 connected to an oxygen tank 26 by a line 27.
- the gas-liquid contactor 2 is a co-current contactor formed by a column filled with packing elements ensuring a high exchange surface, more particularly a static mixer.
- this gas-liquid contactor can be counter-current and formed by a column with packing or plates, in which the liquid enters at the top and flows gravitatively downward, while the gas is that is, the ozone is supplied at the bottom of the column.
- the buffer tank 4 is also mounted in a filtration loop 28 and comprises a suction pipe 29 connected to the bottom of the buffer tank 4 and to a pump 30, and a discharge pipe 31 between the pump 30 and the upper part of the tank buffer 4, a valve 32, a filter 33, a second valve 34 and a third valve 35 being successively mounted in this discharge conduit 31.
- the filter 33 is short-circuited by a conduit 36 with a valve 37.
- a conduit 38 is connected to the conduit 31.
- This conduit 38 comprises a valve 39 and is connected to an effluent storage tank 40.
- the exhaust pipe 11 is connected by a pipe 41 to the buffer tank 4.
- the solution is heated to the above temperature in the latter tank.
- This decontamination solution is an acidic solution of cerium sulphate therefore containing Ce 4+.
- the principle of decontamination is based on the oxidizing nature of the Ce 4 + / Ce3 + couple. When this solution is brought into contact with steels, it leads to their corrosion by oxidation reactions of metals and oxides.
- the electrolyte In order to minimize the consumption of IV cerium and ensure maximum stability of the solution, the electrolyte must be chosen with care.
- the most suitable electrolyte according to the invention is sulfuric acid, although nitric acid can also be used.
- the total concentration of cerium is between 0.1 and 50 g / 1 and preferably between 1 and 15 g / 1, for example of the order of 0.05 M and the sulfuric acid concentration between 10 ⁇ and 2 M , preferably between 1 and 2 M, for example 1 M.
- the above-mentioned decontamination solution circulates continuously through the circulation loop 5, that is to say, the solution overflowing through the overflow 8 returns to the buffer tank 4, from where it is pumped via the suction 19 by pump 20. - 9 -
- the oxygen in the reservoir 26 is charged with ozone, for example with a concentration of 5 to 500 g of ozone per m, in the ozonator 25, and is injected towards the line 27 at the bottom of the contactor 2.
- the ratio between ceric sulfate (Ce 4+) and cerous sulfate (Ce) is between 20 and 0.1 and preferably between 3 and 0.5.
- the Ce 4 + / Ce3 + ratio must be maintained at a value greater than or equal to 1 to guarantee a sufficient attack speed.
- the ozone flow is adjusted according to the particular application and is essentially a function of the treated surface, the attack speed of the material of the parts to be decontaminated and the regeneration yield.
- the oxygen loaded with residual ozone leaving through the exhaust pipe 11 is first cooled in the condenser 13 to condense the acid vapors which are evacuated via the - 10 -
- the flow rate of the solution pumped by the pump 20 depends on the particular application but is generally between 10 and 100 replenishments of the content of the decontamination tank 1.
- part of the oxides detaches without dissolving.
- the solution is filtered after decontamination.
- the valves 32, 34 and 35 are open and the pump 30 is started.
- the solution is pumped from the buffer tank 4 and discharged through the filter 33 to this buffer tank 4.
- the filtration rate is normally from 1 to 10 replenishments of the contents of tank 4 per hour.
- the ultrasonic probes 7 plunging into the bath of the tank 1 can emit ultrasound. These ultrasound speeds up - 11 -
- the residence time of the parts to be decontaminated in the decontamination tank 1 can be reduced up to 1 to 8 hours, depending on the particular application.
- the solution in the decontamination tank 1 is transferred to the buffer tank 4 after opening the valve 23 and the basket 18 is removed from the tank 1, drained and transferred to a rinsing tank.
- the cleaning of the parts in the rinsing tank is preferably carried out using ultrasonic cleaning combined with closed circuit filtration of the rinsing solution.
- the basket 18 is removed from the rinsing tank and is drained and the parts are removed from the basket 18 and checked.
- these parts are either disposed of as non-radioactive waste, or recycled for a second pass through the decontamination device, or disposed of as radioactive waste or even discharged to a metal waste melting installation.
- the solution is transferred from the - 12 -
- the device described above can be used to decontaminate the equipment on site. It is sufficient to connect the circulation loop 5 via a pump and temporary conduits to this equipment.
- the contactor 2 allows an optimal extraction of ozone from the gas phase, that is to say from oxygen or air, and a sufficient contact time between the gas loaded with ozone and the solution.
Abstract
Description
Claims
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE9800132 | 1998-02-20 | ||
BE9800132A BE1011754A3 (en) | 1998-02-20 | 1998-02-20 | Method and metal surfaces decontamination installation. |
PCT/BE1999/000019 WO1999043006A1 (en) | 1998-02-20 | 1999-02-16 | Method and installation for decontaminating metallic surfaces |
Publications (2)
Publication Number | Publication Date |
---|---|
EP1060476A1 true EP1060476A1 (en) | 2000-12-20 |
EP1060476B1 EP1060476B1 (en) | 2006-11-15 |
Family
ID=3891111
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP99903548A Expired - Lifetime EP1060476B1 (en) | 1998-02-20 | 1999-02-16 | Method and installation for decontaminating metallic surfaces |
Country Status (6)
Country | Link |
---|---|
EP (1) | EP1060476B1 (en) |
AT (1) | ATE345571T1 (en) |
BE (1) | BE1011754A3 (en) |
DE (1) | DE69933997T2 (en) |
ES (1) | ES2277425T3 (en) |
WO (1) | WO1999043006A1 (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2792763B1 (en) * | 1999-04-26 | 2004-05-28 | Commissariat Energie Atomique | METHOD FOR RADIOACTIVE DECONTAMINATION OF STEEL WALL AND DEVICE FOR RADIOACTIVE DECONTAMINATION |
JP2003098294A (en) * | 2001-09-27 | 2003-04-03 | Hitachi Ltd | Decontamination method using ozone and apparatus therefor |
KR101086600B1 (en) * | 2006-02-09 | 2011-11-23 | 가부시끼가이샤 도시바 | Chemical decontamination apparatus and decontamination method therein |
Family Cites Families (12)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CH619807A5 (en) * | 1976-04-07 | 1980-10-15 | Foerderung Forschung Gmbh | |
CA1229480A (en) * | 1983-07-12 | 1987-11-24 | Alexander P. Murray | Ozone oxidation of deposits in cooling systems of nuclear reactors |
SE451915B (en) * | 1984-03-09 | 1987-11-02 | Studsvik Energiteknik Ab | PROCEDURE FOR DECOMPOSITION OF PRESSURE WATER REACTORS |
FR2565021B1 (en) * | 1984-05-25 | 1992-03-06 | Toshiba Kk | APPARATUS FOR DECONTAMINATION OF RADIOACTIVE METAL WASTE |
ZA853531B (en) * | 1984-05-29 | 1985-12-24 | Westinghouse Electric Corp | Ceric acid decontamination of nuclear reactors |
DE3578635D1 (en) * | 1984-10-31 | 1990-08-16 | Kraftwerk Union Ag | METHOD FOR CHEMICAL DECONTAMINATION OF LARGE COMPONENTS AND SYSTEMS MADE OF METAL MATERIALS OF CORE REACTORS. |
FR2590716B1 (en) * | 1985-11-26 | 1992-05-15 | Electricite De France | PROCESS FOR DECONTAMINATION OF NUCLEAR REACTOR WALLS, IN PARTICULAR WALLS OF THE PRIMARY CIRCUIT OF NUCLEAR REACTORS WITH PRESSURIZED WATER CIRCUIT |
SE465142B (en) * | 1988-08-11 | 1991-07-29 | Studsvik Ab | PROCEDURES DISCONTINUATE CORROSION PRODUCTS IN NUCLEAR POWER REACTORS |
JPH0727073B2 (en) * | 1990-03-20 | 1995-03-29 | 森川産業株式会社 | Decontamination method and decontamination apparatus for objects contaminated with radioactivity, and decontamination method and decontamination apparatus for materials used for the decontamination |
FR2687005B1 (en) * | 1992-02-03 | 1994-10-21 | Framatome Sa | PROCESS AND INSTALLATION FOR DECONTAMINATION OF THE PRIMARY PART OF A STEAM GENERATOR USING A NUCLEAR REACTOR WITH REGULAR WATER UNDER PRESSURE. |
FR2701155B1 (en) * | 1993-02-02 | 1995-04-21 | Framatome Sa | Method and installation for decontamination of used lids of light water nuclear reactor vessels. |
FR2706217A1 (en) * | 1993-06-08 | 1994-12-16 | Framatome Sa | Method for rehabilitating a heat exchanger in a nuclear power plant, in particular a heat exchanger in the auxiliary cooling circuit of a shutdown nuclear reactor. |
-
1998
- 1998-02-20 BE BE9800132A patent/BE1011754A3/en not_active IP Right Cessation
-
1999
- 1999-02-16 ES ES99903548T patent/ES2277425T3/en not_active Expired - Lifetime
- 1999-02-16 AT AT99903548T patent/ATE345571T1/en not_active IP Right Cessation
- 1999-02-16 WO PCT/BE1999/000019 patent/WO1999043006A1/en active IP Right Grant
- 1999-02-16 DE DE69933997T patent/DE69933997T2/en not_active Expired - Lifetime
- 1999-02-16 EP EP99903548A patent/EP1060476B1/en not_active Expired - Lifetime
Non-Patent Citations (1)
Title |
---|
See references of WO9943006A1 * |
Also Published As
Publication number | Publication date |
---|---|
DE69933997D1 (en) | 2006-12-28 |
DE69933997T2 (en) | 2007-05-10 |
ATE345571T1 (en) | 2006-12-15 |
EP1060476B1 (en) | 2006-11-15 |
WO1999043006A1 (en) | 1999-08-26 |
ES2277425T3 (en) | 2007-07-01 |
BE1011754A3 (en) | 1999-12-07 |
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