Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
GB2134694A - Improvements in and relating to the treatment of radioactive effluents - Google Patents
[go: Go Back, main page]

GB2134694A - Improvements in and relating to the treatment of radioactive effluents - Google Patents

Improvements in and relating to the treatment of radioactive effluents Download PDF

Info

Publication number
GB2134694A
GB2134694A GB08301074A GB8301074A GB2134694A GB 2134694 A GB2134694 A GB 2134694A GB 08301074 A GB08301074 A GB 08301074A GB 8301074 A GB8301074 A GB 8301074A GB 2134694 A GB2134694 A GB 2134694A
Authority
GB
United Kingdom
Prior art keywords
drum
effluent
radioactive
precipitates
cement
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Withdrawn
Application number
GB08301074A
Other versions
GB8301074D0 (en
Inventor
Richard Adrian Carr
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
British Nuclear Fuels Ltd
Original Assignee
British Nuclear Fuels Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by British Nuclear Fuels Ltd filed Critical British Nuclear Fuels Ltd
Priority to GB08301074A priority Critical patent/GB2134694A/en
Publication of GB8301074D0 publication Critical patent/GB8301074D0/en
Publication of GB2134694A publication Critical patent/GB2134694A/en
Withdrawn legal-status Critical Current

Links

Classifications

    • BPERFORMING OPERATIONS; TRANSPORTING
    • B01PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01DSEPARATION
    • B01D35/00Filtering devices having features not specifically covered by groups B01D24/00 - B01D33/00, or for applications not specifically covered by groups B01D24/00 - B01D33/00; Auxiliary devices for filtration; Filter housing constructions
    • B01D35/06Filters making use of electricity or magnetism
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/10Processing by flocculation

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Water Supply & Treatment (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Removal Of Specific Substances (AREA)
  • Water Treatment By Electricity Or Magnetism (AREA)

Abstract

Radioactive fines in an effluent stream are trapped in a magnetic filter comprising a drum containing a wire mesh and located between the poles of a magnet. Thereafter the drum is filled with cement to encapsulate the radioactive fines and form a solid block for subsequent disposal or storage.

Description

SPECIFICATION Improvements in and relating to the treatment of radioactive effluents The present invention concerns the treatment of radioactive effluent.
It is known to treat radioactive effluent, for example effluent arising from the reprocessing of irradiated nuclear fuel, with reagents to produce precipitates which are capable of retaining the radioactive nuclides in the effluent. Thereafter the precipitates carrying the radioactive nuclides can be separated from the remainder of the effluent. It is also known to encapsulate radioactive nuclides within a solid matrix, such as cement, for subsequent storage and disposal.
According to the present invention a method of treating radioactive effluent comprises forming precipitates in the effluent capable of retaining radionuclides, passing the effluent through a filter to trap the precipitates and radionuclides and filling the filter with a solid matrix to encapsulate the trapped precipitates and radionuclides.
The precipitates can be magnetite which is capable of magnetic filtration. A convenient form of filter can comprise a drum filled with a wire mesh or wool and positioned between the poles of a magnet. The encapsulating medium can be cement.
The invention will be described further, by way of example, with reference to the accompanying drawing which is a schematic diagram of an embodiment of a magnetic filter.
A drum or container 1, packed with wire wool or mesh 2, is located between the poles of a magnet 3. The mesh 2 can occupy from 2% to 5% of the volume of the drum. The magnet can be a permanent magnet or an electromagnet. The top of the drum 1 is closed and sealed by a lid 4 and an inlet feed pipe 5 passes through the lid to terminate adjacent the bottom of the drum. The wire wool is supported on a distributor plate 6 which serves to spread the flow of liquid emerging from the pipe 5 in a substantially even manner over the diameter of the drum. The lid 4 also carries an outlet pipe 7.
In use, an effluent stream, to be filtered and containing a magnetic precipitate, such as magnetite, carrying radioactive species is introduced into thë drum through the feed pipe 5.
The flow passes upwardly through the wire wool 2 and the magnetite carrying the radioactive species is trapped in the wire wool due to the field created by the magnet 3. The liquid emerging through the outlet 7 is substantially free of radioactive species.
The flow is continued until the wire wool matrix within the drum is saturated with magnetite and typically this can occur when the magnetite occupies about 20% of the void space within the drum. Thereafter the flow of liquid into the drum is discontinued and a fluid cement mixture is introduced into the drum through the inlet pipe 5. The cement displaces liquid in the drum through the outlet pipe and encapsulates the magnetite which remains attached to the wire mesh as a result of the magnetic field of the magnet. The cement supply is discontinued when the drum is filled with cement. The drum is removed from the magnet and the concrete sets into a solid block incorporating the magnetite and radioactive species. The concrete-filled drum can then be stored or disposed of in an accepted manner.
A suitable cement mixture can comprise Portland cement and pulverised fly ash. The wire mesh conveniently can be a mild or stainless steel matrix with filament size of up to 1.5 mm diameter. The drum can be a standard size, 500 or 1000 litre capacity and the magnetic field applied by the magnet can be between 0.1 and 0.5 Tesla.
Claims (Filed on 9 Jan 84) 1. A method of treating radioactive effluent comprising forming precipitates in the effluent capable of retaining radionuclides, passing the effluent through a filter to trap the precipitates and radionuclides and filling the filter with a solid matrix to encapsulate the trapped precipitates and radionuclides.
2. A method as claimed in claim 1 which comprises magnetically trapping the precipitates and radionuclides.
3. A method as claimed in claim 1 or 2 which comprises encapsulating the trapped precipitates and radionuclides in cement.
4. A method of treating radioactive effluent substantially as herein described with reference to the accompanying drawing.
5. Apparatus for treating radioactive effluent substantially as herein described with reference to and as illustrated in the accompanying drawing.
**WARNING** end of DESC field may overlap start of CLMS **.

Claims (5)

**WARNING** start of CLMS field may overlap end of DESC **. SPECIFICATION Improvements in and relating to the treatment of radioactive effluents The present invention concerns the treatment of radioactive effluent. It is known to treat radioactive effluent, for example effluent arising from the reprocessing of irradiated nuclear fuel, with reagents to produce precipitates which are capable of retaining the radioactive nuclides in the effluent. Thereafter the precipitates carrying the radioactive nuclides can be separated from the remainder of the effluent. It is also known to encapsulate radioactive nuclides within a solid matrix, such as cement, for subsequent storage and disposal. According to the present invention a method of treating radioactive effluent comprises forming precipitates in the effluent capable of retaining radionuclides, passing the effluent through a filter to trap the precipitates and radionuclides and filling the filter with a solid matrix to encapsulate the trapped precipitates and radionuclides. The precipitates can be magnetite which is capable of magnetic filtration. A convenient form of filter can comprise a drum filled with a wire mesh or wool and positioned between the poles of a magnet. The encapsulating medium can be cement. The invention will be described further, by way of example, with reference to the accompanying drawing which is a schematic diagram of an embodiment of a magnetic filter. A drum or container 1, packed with wire wool or mesh 2, is located between the poles of a magnet 3. The mesh 2 can occupy from 2% to 5% of the volume of the drum. The magnet can be a permanent magnet or an electromagnet. The top of the drum 1 is closed and sealed by a lid 4 and an inlet feed pipe 5 passes through the lid to terminate adjacent the bottom of the drum. The wire wool is supported on a distributor plate 6 which serves to spread the flow of liquid emerging from the pipe 5 in a substantially even manner over the diameter of the drum. The lid 4 also carries an outlet pipe 7. In use, an effluent stream, to be filtered and containing a magnetic precipitate, such as magnetite, carrying radioactive species is introduced into thë drum through the feed pipe 5. The flow passes upwardly through the wire wool 2 and the magnetite carrying the radioactive species is trapped in the wire wool due to the field created by the magnet 3. The liquid emerging through the outlet 7 is substantially free of radioactive species. The flow is continued until the wire wool matrix within the drum is saturated with magnetite and typically this can occur when the magnetite occupies about 20% of the void space within the drum. Thereafter the flow of liquid into the drum is discontinued and a fluid cement mixture is introduced into the drum through the inlet pipe 5. The cement displaces liquid in the drum through the outlet pipe and encapsulates the magnetite which remains attached to the wire mesh as a result of the magnetic field of the magnet. The cement supply is discontinued when the drum is filled with cement. The drum is removed from the magnet and the concrete sets into a solid block incorporating the magnetite and radioactive species. The concrete-filled drum can then be stored or disposed of in an accepted manner. A suitable cement mixture can comprise Portland cement and pulverised fly ash. The wire mesh conveniently can be a mild or stainless steel matrix with filament size of up to 1.5 mm diameter. The drum can be a standard size, 500 or 1000 litre capacity and the magnetic field applied by the magnet can be between 0.1 and 0.5 Tesla. Claims (Filed on 9 Jan 84)
1. A method of treating radioactive effluent comprising forming precipitates in the effluent capable of retaining radionuclides, passing the effluent through a filter to trap the precipitates and radionuclides and filling the filter with a solid matrix to encapsulate the trapped precipitates and radionuclides.
2. A method as claimed in claim 1 which comprises magnetically trapping the precipitates and radionuclides.
3. A method as claimed in claim 1 or 2 which comprises encapsulating the trapped precipitates and radionuclides in cement.
4. A method of treating radioactive effluent substantially as herein described with reference to the accompanying drawing.
5. Apparatus for treating radioactive effluent substantially as herein described with reference to and as illustrated in the accompanying drawing.
GB08301074A 1983-01-14 1983-01-14 Improvements in and relating to the treatment of radioactive effluents Withdrawn GB2134694A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB08301074A GB2134694A (en) 1983-01-14 1983-01-14 Improvements in and relating to the treatment of radioactive effluents

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB08301074A GB2134694A (en) 1983-01-14 1983-01-14 Improvements in and relating to the treatment of radioactive effluents

Publications (2)

Publication Number Publication Date
GB8301074D0 GB8301074D0 (en) 1983-02-16
GB2134694A true GB2134694A (en) 1984-08-15

Family

ID=10536375

Family Applications (1)

Application Number Title Priority Date Filing Date
GB08301074A Withdrawn GB2134694A (en) 1983-01-14 1983-01-14 Improvements in and relating to the treatment of radioactive effluents

Country Status (1)

Country Link
GB (1) GB2134694A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2165085A (en) * 1984-09-28 1986-04-03 British Nuclear Fuels Plc Improvements in containers for encapsulating wastes
RU2174260C2 (en) * 1999-10-13 2001-09-27 Российский Федеральный Ядерный Центр - Всероссийский Научно-Исследовательский Институт Экспериментальной Физики Method for recovery and disposal of spent filters
RU2292094C2 (en) * 2005-02-07 2007-01-20 Федеральное государственное унитарное предприятие УРАЛЬСКИЙ ЭЛЕКТРОХИМИЧЕСКИЙ КОМБИНАТ Method and unit for pre-storage or pre-burial treatment of spent filters
US20140231353A1 (en) * 2011-07-21 2014-08-21 Jnc Corporation Method and Apparatus for Removing Cesium Ion from Water

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1180020A (en) * 1966-12-20 1970-02-04 Bbc Brown Boveri & Cie Apparatus and Method for Separating a Liquid from Solid Substances Contained Therein.
GB1188396A (en) * 1967-12-11 1970-04-15 Belge Pour L Ind Nucleaire S A Treatment of Radioactive Liquids
GB1525068A (en) * 1975-10-16 1978-09-20 Kraftwerk Union Ag Final storage of a radioactively contaminated article
EP0000181A1 (en) * 1977-06-24 1979-01-10 Ingenieurbüro Stecker Process and apparatus for solidifying toxic and waste materials, in particular radioactive materials.
GB2037058A (en) * 1978-10-27 1980-07-02 Cnen Process and apparatus for the continuous purification of contaminated fluids and for conditioning the resulting concentrates
GB2050186A (en) * 1979-05-14 1981-01-07 Meyer Ag Maschf Filtration process

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1180020A (en) * 1966-12-20 1970-02-04 Bbc Brown Boveri & Cie Apparatus and Method for Separating a Liquid from Solid Substances Contained Therein.
GB1188396A (en) * 1967-12-11 1970-04-15 Belge Pour L Ind Nucleaire S A Treatment of Radioactive Liquids
GB1525068A (en) * 1975-10-16 1978-09-20 Kraftwerk Union Ag Final storage of a radioactively contaminated article
EP0000181A1 (en) * 1977-06-24 1979-01-10 Ingenieurbüro Stecker Process and apparatus for solidifying toxic and waste materials, in particular radioactive materials.
GB2037058A (en) * 1978-10-27 1980-07-02 Cnen Process and apparatus for the continuous purification of contaminated fluids and for conditioning the resulting concentrates
GB2050186A (en) * 1979-05-14 1981-01-07 Meyer Ag Maschf Filtration process

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2165085A (en) * 1984-09-28 1986-04-03 British Nuclear Fuels Plc Improvements in containers for encapsulating wastes
RU2174260C2 (en) * 1999-10-13 2001-09-27 Российский Федеральный Ядерный Центр - Всероссийский Научно-Исследовательский Институт Экспериментальной Физики Method for recovery and disposal of spent filters
RU2292094C2 (en) * 2005-02-07 2007-01-20 Федеральное государственное унитарное предприятие УРАЛЬСКИЙ ЭЛЕКТРОХИМИЧЕСКИЙ КОМБИНАТ Method and unit for pre-storage or pre-burial treatment of spent filters
US20140231353A1 (en) * 2011-07-21 2014-08-21 Jnc Corporation Method and Apparatus for Removing Cesium Ion from Water
US9659678B2 (en) * 2011-07-21 2017-05-23 Jnc Corporation Method for removing cesium ions from water

Also Published As

Publication number Publication date
GB8301074D0 (en) 1983-02-16

Similar Documents

Publication Publication Date Title
US3749917A (en) Device for encapsulating a radioactive resin-water slurry
KR102058277B1 (en) Liquid radioactive waste treatment and recovery method thereof
US3764553A (en) Removal of radioisotopes from waste solutions
JP3009828B2 (en) High volume solidification method for high level radioactive liquid waste
CN102859608A (en) Isotope-specific separation and vitrification using ion-specific media
JP2002267795A (en) Method and device for disposing radioactive material- containing waste liquid
GB2134694A (en) Improvements in and relating to the treatment of radioactive effluents
RU2118856C1 (en) method and apparatus for removing strontium and cesium radionuclides from solutions
JPH0527094A (en) Treatment method for solid radioactive waste
Carr Improvements in and relating to the treatment of radioactive effluents
Crosby III et al. New techniques of water sampling for carbon 14 analysis
KR20030043126A (en) A method for increasing the removal efficiency of radio nuclides using acetic acid and sodium acetate on dicomtaminating the soil contaminated radio nuclides by electrokinetic method
JP2002031697A (en) Method for treating radioactive waste liquid
JP2004028903A (en) Device for separating radioactive waste liquid and disposal system for radioactive ion exchange resin provided with the same
JPS62226000A (en) Radioactive nuclide separation method from ion exchange resin
RU2675251C1 (en) Method for processing liquid radioactive wastes
JP2000038623A (en) Separation of radio active particles, separation system and apparatus for separation
EP0456382A1 (en) A method for the removal of radioisotope cations from an aqueous environment using modified clinoptilolite
JPS56105719A (en) Electromagnetic filter for atomic energy
Bronić et al. Removal of cesium radioisotopes from solutions using granulated zeolites
RU2214013C2 (en) Method for decontaminating radioactive wastes
GB2024498A (en) Method of Treating Radioactive Waste Material
JPS6341438B2 (en)
JP2026036592A (en) Radioactive liquid waste treatment method and radioactive liquid waste treatment system
Sumrall III et al. Removal of radioisotopes from water by slurrying with Yazoo and Zilpha clays

Legal Events

Date Code Title Description
WAP Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1)