GB2319259A - reducing radionucleide contamination of a metallic component - Google Patents
reducing radionucleide contamination of a metallic component Download PDFInfo
- Publication number
- GB2319259A GB2319259A GB9623953A GB9623953A GB2319259A GB 2319259 A GB2319259 A GB 2319259A GB 9623953 A GB9623953 A GB 9623953A GB 9623953 A GB9623953 A GB 9623953A GB 2319259 A GB2319259 A GB 2319259A
- Authority
- GB
- United Kingdom
- Prior art keywords
- metallic component
- radionuclide
- surface contamination
- reducing
- electrolytic liquid
- 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.)
- Withdrawn
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
-
- C—CHEMISTRY; METALLURGY
- C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
- C25F—PROCESSES FOR THE ELECTROLYTIC REMOVAL OF MATERIALS FROM OBJECTS; APPARATUS THEREFOR
- C25F1/00—Electrolytic cleaning, degreasing, pickling or descaling
-
- C—CHEMISTRY; METALLURGY
- C25—ELECTROLYTIC OR ELECTROPHORETIC PROCESSES; APPARATUS THEREFOR
- C25F—PROCESSES FOR THE ELECTROLYTIC REMOVAL OF MATERIALS FROM OBJECTS; APPARATUS THEREFOR
- C25F7/00—Constructional parts, or assemblies thereof, of cells for electrolytic removal of material from objects; Servicing or operating
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Electrochemistry (AREA)
- Materials Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- General Chemical & Material Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Food Science & Technology (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Water Treatment By Electricity Or Magnetism (AREA)
Abstract
Apparatus for reducing radionuclide contamination of a metallic component includes a concentrated spray nozzle 16 mounted on an articulated positioning arm 26 arranged to traverse completely a surface 28 of a component of a nuclear plant upon de-commissioning and subject to radio-active contamination. The nozzle 16 is connected, as a cathode, to an electrical power source 32 to give an electrical current density of approximately 50 amps per tenth square metre with the component connected as an anode. An electrolytic treatment liquid 20, such as 5% nitric acid solution, is discharged through the nozzle 16 to react with at least any metallic oxide surface layer to dislodge or detach any radionuclide particles, such as particles of cobalt 60, attached to the surface 28. The electrolytic treatment liquid 20 drains to a shallow reservoir formed by the component or to a separate reservoir 18 and is then passed to a settling tank 10 and fine filter 20 where the radionuclides settle out or are filtered out and the liquid re-cycled.
Description
METHOD OF, AND APPARATUS FOR,
REDUCING RADIONUCLIDE SURFACE
CONTAMINATION OF A
METALLIC COMPONENT
DESCRIPTION
This invention relates to a method of, and apparatus for, reducing radionuclide surface contamination of a metallic component and, more particularly, to reducing to an acceptable level the amount of radio-active contaminants adhering to surfaces of components of a nuclear plant upon de-commissioning.
Safe disposal as steel debris of components contaminated with radionuclides, such as components from decommissioned nuclear power plant, is difficult. Present disposal techniques are labour and dose intensive and incur high transport and storage costs. Hitherto, component decontamination has been achieved utilising electropolishing or acid pickling techniques involving immersing the component in a bath of electrolyte or acid. However, although the component may be decontaminated to an acceptable level of radio-activity, a relatively large volume of liquid is required, which, in turn, presents difficulties for safe disposal.
According to one aspect of the present invention, there is provided a method of reducing radionuclide surface contamination of a metallic component including subjecting a contaminated surface layer of the component to a concentrated spray of electrolytic liquid flowing in a closed flow circuit, the electrolytic liquid having a composition reactive with metallic oxides present in the contaminated surface layer, applying an electrical current to the concentrated spray to be conducted through the concentrated spray of electrolytic liquid to the metallic component acting as an anode, removing at least the metallic oxides from the contaminated surface layer as reaction products in the electrolytic liquid, removing radionuclide particles dislodged or detached from the contaminated surface layer in suspension in the electrolytic liquid, passing the electrolytic liquid through recovery means arranged to remove radionuclide particles from suspension and re-utilising the electrolytic liquid in the concentrated spray in the closed flow circuit.
In another aspect of the invention, there is provided apparatus including pump means arranged to urge a stream of electrolytic liquid around a closed flow circuit, the closed flow circuit including a concentrated spray nozzle connected as a cathode to a source of direct current electric power, means to traverse the concentrated spray nozzle in close proximity to a radionuclide contaminated surface of a component electrically connected as an anode and reservoir means for collection of the electrolytic liquid following discharge from the concentrated spray nozzle and impingement on the contaminated surface, the reservoir means being connected to an inlet of the pump means.
The invention will now be described, by way of example, with reference to the accompanying, diagrammatic drawing of decontamination equipment 2 positioned to treat a spherical metal vessel 4.
The decontamination equipment 4 includes a closed flow circuit 6 comprising a pump 8, a settling tank 10, a fine filter 12, a delivery conduit 14, a concentrated spray nozzle 16, a reservoir 18 for electrolytic treatment liquid 20 and an uptake conduit 22 connected to the pump 8. The reservoir 18 is formed in a base portion 24 of the spherical metal vessel 4. In other arrangements (not shown) in which the component for decontamination does not have a configuration suitable for the formation of an integral reservoir 18, a tank or vessel is provided to serve as an external reservoir.
As shown, the concentrated spray nozzle 16 is mounted on an articulated positioning arm 26 manoeuverable to traverse the concentrated spray nozzle 16 across the complete interior wall surface 28 of the spherical metal vessel 4, closely adjacent the surface 28. The positioning arm 26 is remotely controlled either through a manually operated mechanical linkage or through a motorized system as a robotic arrangement. Adjacent the concentrated spray nozzle 16, the positioning arm 26 carries a closed circuit television camera and a Geiger counter sensor (not shown) to facilitate visual radioactivity monitoring within the spherical metal vessel 4.
In other arrangements (not shown) the concentrated spray nozzle 16 and associated monitoring equipment is mounted on a pig, for moving through pipework, or is mounted on a moveable robot device, or is fixed whilst the component for decontamination is manipulated to move relative thereto.
Where conditions permit and are suitable an array of concentrated spray nozzles may be utilised to produce an extended spray pattern.
The electrolytic treatment liquid 20 is selected to be reactive with a metallic oxide surface layer formed on the wall surface 28 during the service life of the component. A typical surface layer may contain oxides of iron, nickel, chromium, manganese and the like. In addition, the electrolytic treatment liquid is selected from liquid compositions giving an enhanced electrolytic effect. Whilst a 5% nitric acid solution is favoured, other strengths or other acids, such as oxalic acid or phosphoric acid, or caustic alkali solutions, such as sodium hydroxide solution, may be utilised.
The concentrated spray nozzle 16 is provided with an electrically insulated mounting on the positioning arm 26 and is connected through a lead 30 to a source 32 of direct current electrical power to serve as a cathode. The electrical power supplied to the concentrated spray nozzle serving as a cathode is in the range of between 1 and 150 amps per tenth of a square metre with a preferred current density of approximately 50 amps per tenth of a square metre. The electrical current is conducted through the concentrated spray to the spherical metal vessel 4, which, in turn, is connected to a positive earth terminal 34 to serve as an anode.
In operation, a metallic component, such as the spherical metal vessel 4, from decommissioned nuclear plant and requiring to be treated to reduce the radio-activity emanating from radionuclides deposited in the metallic oxide surface layer formed on the component during service in the nuclear plant is positioned in a decommissioning zone and in a manner permitting access of the concentrated spray nozzle to the complete contaminated surfaces. Thus, as shown, the spherical metal vessel 4 is located relative to the positioning arm 16. The base portion 24 of the vessel 4 is sealed to provide the reservoir 18 of relatively shallow depth so as not to impede the action of the concentrated spray upon the base portion 24. The spherical metal vessel 4 is connected to the positive earth terminal 34.
Electrolytic treatment liquid 20 is then supplied from a supply tank (not shown) to the pumps, which is energised, and the electrolytic treatment liquid 20 pumped around the flow circuit 6 to discharge at the concentrated spray nozzle 16 closely adjacent the interior wall surface 28.
Electrolytic treatment liquid 20 collecting in the reservoir 18 is returned to the pump 8 through the uptake conduit 22.
The electrolytic treatment liquid reacts with the metallic oxides in the contaminated surface layer and the underlying metallic surface to dissolve the metallic oxides and thereby tends to dislodge or detach any radionuclide particles, such as particles of cobalt 60, attached to the surface 28, which then become suspended and entrained in the electrolytic treatment liquid. The reactions and the dislodgment or detachment of the radionuclides are enhanced by the electrolytic action arising on the application of the electric current to the concentrated spray nozzle 16 serving as a cathode. In the flow circuit 6, the electrolytic treatment liquid 20 passes through the settling tank 10 and fine filter 12 where the radionuclides settle out or are filtered out. In alternative arrangements, not shown, alternative means may be utilised to remove the radionuclides from the electrolytic treatment liquid 20.
Such means may include distillation, centrifuges or chemical means. The chemical means may also serve to effect removal of radionuclides dissolved in the treatment liquid 20.
Following contacting the complete interior wall surface 28 with the electrolytic treatment liquid, the Geiger counter sensor mounted on the positioning arm 26 is utilised to monitor the level of residual radio-activity and, if necessary, treatment of specific areas, such as welds, repeated, until the complete component has been reduced to an acceptable level of radio-activity. At this juncture, or even preparatory to checking the level of residual radioactivity, the reservoir 18 and the flow circuit are drained and washed down. Particles arrested in the settling tank 10 and fine filter 12, which largely will be radionuclides are removed, together with, if necessary, the settling tank 10 and fine filter 12, for disposal in an appropriate manner.
It will be appreciated that the above described treatment method may be utilised with a component in situ where provision may be made for contacting the required surfaces with the concentrated spray of electrolytic treatment liquid, which is then readily recovered subsequent to contacting the component and for making the requisite electrical connections.
Claims (24)
1. A method of reducing radionuclide surface
contamination of a metallic component including
subjecting a contaminated surface layer of the
component to a concentrated spray of electrolytic
liquid flowing in a closed flow circuit, the
electrolytic liquid having a composition reactive
with metallic oxides present in the contaminated
surface layer, applying an electrical current to
the concentrated spray to be conducted through the
concentrated spray to the metallic component
acting as an anode, removing at least the metallic
oxides from the contaminated surface layer as
reaction products in the electrolytic liquid,
removing radionuclides particles dislodged or
detached from the contaminated surface layer in
suspension in the electrolytic liquid, passing the
electrolytic liquid through recovery means
arranged to remove radionuclide particles from
suspension and re-utilising the electrolytic
liquid in the concentrated spray in the closed
flow circuit.
2. A method of reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 1, wherein the electrolytic liquid has an
acidic composition.
3. A method of reducing radionuclide surface
contamination of a metallic radionuclide component
as claimed in Claim 2, wherein the electrolytic
liquid is dilute nitric acid.
4. A method of reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 3, wherein the electrolytic liquid is a
5% solution of nitric acid.
5. A method of reducing radionuclide surface
contamination of a metallic component as claimed
in any proceeding Claim, wherein the concentrated
spray is connected, as a cathode, to a source of
electrical power with the component connected as
an anode and an electrical current of a density of
between 1 and 150 amps per tenth square metre is
applied through the concentrated spray.
6. A method of reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 5, wherein an electrical current density
of approximately 50 amps per tenth square metre is
applied through the concentrated spray.
7. An method of reducing radionuclide surface contamination of a metallic component as claimed
in any preceding Claim, wherein the suspended
radionuclide particles are removed from the
following electrolytic liquid through mechanical
separating means.
8. A method of reducing radionuclide surface
contaminated of a metallic component as claimed
in Claim 7, wherein the radionuclide particles are
permitted to settle out of suspension in a
settling tank.
9. A method of reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 8, wherein radionuclide particles
remaining in suspension downstream of the settling
tank are removed from the electrolytic liquid by
passage through a fine filter.
10. A method of reducing radionuclide surface
contamination of a metallic component as claimed
in any proceeding Claim, wherein the metallic
component is arranged to form a reservoir for the
collection of the electrolytic liquid as a part of
the closed flow circuit.
11. Apparatus for reducing radionuclide surface
contamination of a metallic component including a
pump means arranged to urge a stream of
electrolytic liquid around a closed flow circuit,
the closed flow circuit including a concentrated
spray nozzle connected as a cathode to a source of
direct current electrical power, means to traverse
the concentrated spray nozzle in close proximity
to a radionuclide contaminated surface of a
component connected as an anode and reservoir
means for collection of the electrolytic liquid
following discharge from the concentrated spray
nozzle and impingement on the contaminated
surface, the reservoir means being connected to an
inlet of the pump means.
12. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 11, wherein the closed flow circuit
includes mechanical separating means adapted to
separate particles suspended in the flowing
electrolytic liquid from the electrolytic liquid.
13. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 12, wherein the mechanical separating
means includes a settling tank.
14. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 12 or Claim 13, wherein the mechanical
separating means includes a fine filter.
15. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in any one of Claims 11 to 14, wherein the
electrolytic liquid is acidic.
16. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 15, wherein the electrolytic liquid is
dilute nitric acid.
17. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 16, wherein the electrolytic liquid is a
5% solution of nitric acid.
18. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in any one of Claims 11 to 17, wherein the
concentrated spray nozzle is connected to a source
of electrical power arranged to deliver an
electrical current density in the range of 1 to
150 amps per tenth square metre.
19. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in Claim 18, wherein the source of electrical
power is arranged to deliver an electrical current
density of approximately 50 amps per tenth square
metre.
20. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in any one of Claims 11 to 19, wherein the
metallic component is arranged to form the
reservoir means.
21. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in any one of Claims 11 to 20, wherein the
concentrated spray nozzle is mounted on a
positioning arm operable to traverse the
concentrated spray nozzle across the complete
contaminated surface in close proximity to the
surface.
22. Apparatus for reducing radionuclide surface
contamination of a metallic component as claimed
in any one of Claim 11 to 21, wherein the
concentrated spray nozzle is mounted on a robotic
device enabling the metallic component to be
treated in a location as occupied by the metallic
component when in service as a part of a nuclear
plant.
23. A method of reducing radionuclide surface
contamination of a metallic component
substantially as hereinbefore described with
reference to the accompanying drawing.
24. Apparatus for reducing radionuclide surface
contamination of a metallic component arranged and
adapted to operate substantially as hereinbefore
described with reference to the accompanying
drawing.
Priority Applications (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB9623953A GB2319259A (en) | 1996-11-15 | 1996-11-15 | reducing radionucleide contamination of a metallic component |
| AU49586/97A AU4958697A (en) | 1996-11-15 | 1997-11-14 | Reducing radionuclide surface contamination of a metallic component |
| PCT/GB1997/003134 WO1998022953A1 (en) | 1996-11-15 | 1997-11-14 | Reducing radionuclide surface contamination of a metallic component |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB9623953A GB2319259A (en) | 1996-11-15 | 1996-11-15 | reducing radionucleide contamination of a metallic component |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB9623953D0 GB9623953D0 (en) | 1997-01-08 |
| GB2319259A true GB2319259A (en) | 1998-05-20 |
Family
ID=10803105
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB9623953A Withdrawn GB2319259A (en) | 1996-11-15 | 1996-11-15 | reducing radionucleide contamination of a metallic component |
Country Status (3)
| Country | Link |
|---|---|
| AU (1) | AU4958697A (en) |
| GB (1) | GB2319259A (en) |
| WO (1) | WO1998022953A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2819622A1 (en) * | 2001-01-17 | 2002-07-19 | Maintenance Nucleaire Soc D | Decontamination procedure, for inner surfaces of hollow radioactive components, uses chemical attack solution sprayed under pressure and recuperated |
| WO2008110587A1 (en) * | 2007-03-13 | 2008-09-18 | Novo Nordisk A/S | An electrolytic cip-cleaning process for removing impurities from the inner surface of a metallic container |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US6264336B1 (en) | 1999-10-22 | 2001-07-24 | 3M Innovative Properties Company | Display apparatus with corrosion-resistant light directing film |
| US6590711B1 (en) | 2000-04-03 | 2003-07-08 | 3M Innovative Properties Co. | Light directing construction having corrosion resistant feature |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60174899A (en) * | 1983-10-18 | 1985-09-09 | Toshiba Corp | Polishing device for metallic surface |
| GB2174105A (en) * | 1985-03-11 | 1986-10-29 | Oilfield Inspection Services | Cleaning subsea surfaces |
| US4663085A (en) * | 1984-05-25 | 1987-05-05 | Kabushiki Kaisha Toshiba | Apparatus for decontamination of radiation contaminated metallic waste |
| US5386078A (en) * | 1993-02-01 | 1995-01-31 | Deco-Hanulik Ag | Process for decontaminating radioactive metal surfaces |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1142776A (en) * | 1967-09-29 | 1969-02-12 | Szmuel Raviv | Decontamination of radioactively contaminated equipment |
| US4318786A (en) * | 1980-03-10 | 1982-03-09 | Westinghouse Electric Corp. | Electrolytic decontamination |
| DE3136187C2 (en) * | 1981-09-12 | 1988-08-18 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Method and device for cleaning the inner walls of metallic pipe systems by electropolishing with the aid of moving electrodes |
| DE3345278A1 (en) * | 1983-12-14 | 1985-06-27 | Kraftwerk Union AG, 4330 Mülheim | DEVICE FOR ELECTROPOLISHING THE INTERNAL SURFACE OF HOLLOW CYLINDRICAL BODIES |
| US4481090A (en) * | 1984-01-23 | 1984-11-06 | The United States Of America As Represented By The United States Department Of Energy | Decontaminating metal surfaces |
| FR2561672B1 (en) * | 1984-03-21 | 1989-09-01 | Travaux Milieu Ionisant | ELECTROLYSIS DEVICE, ESPECIALLY FOR RADIOACTIVE DECONTAMINATION OF METAL SURFACES |
| EP0436528B1 (en) * | 1988-10-10 | 1993-02-24 | Siemens Aktiengesellschaft | Electric surface-polishing device |
-
1996
- 1996-11-15 GB GB9623953A patent/GB2319259A/en not_active Withdrawn
-
1997
- 1997-11-14 AU AU49586/97A patent/AU4958697A/en not_active Abandoned
- 1997-11-14 WO PCT/GB1997/003134 patent/WO1998022953A1/en active Application Filing
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS60174899A (en) * | 1983-10-18 | 1985-09-09 | Toshiba Corp | Polishing device for metallic surface |
| US4663085A (en) * | 1984-05-25 | 1987-05-05 | Kabushiki Kaisha Toshiba | Apparatus for decontamination of radiation contaminated metallic waste |
| GB2174105A (en) * | 1985-03-11 | 1986-10-29 | Oilfield Inspection Services | Cleaning subsea surfaces |
| US5386078A (en) * | 1993-02-01 | 1995-01-31 | Deco-Hanulik Ag | Process for decontaminating radioactive metal surfaces |
Non-Patent Citations (2)
| Title |
|---|
| DD 261867 A & WPI Accession no 89-100497/14 * |
| Patent Abstracts of Japan vol10 (C-235) (2080) page 40, 1986 & JP 60 174899 A * |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2819622A1 (en) * | 2001-01-17 | 2002-07-19 | Maintenance Nucleaire Soc D | Decontamination procedure, for inner surfaces of hollow radioactive components, uses chemical attack solution sprayed under pressure and recuperated |
| WO2002058076A1 (en) * | 2001-01-17 | 2002-07-25 | Societe De Maintenance Nucleaire 'somanu' | Method and device for radioactive decontamination of a surface located inside an hollow body |
| WO2008110587A1 (en) * | 2007-03-13 | 2008-09-18 | Novo Nordisk A/S | An electrolytic cip-cleaning process for removing impurities from the inner surface of a metallic container |
Also Published As
| Publication number | Publication date |
|---|---|
| GB9623953D0 (en) | 1997-01-08 |
| WO1998022953A1 (en) | 1998-05-28 |
| AU4958697A (en) | 1998-06-10 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |