CA1154885A - Method of decontaminating nuclear power plant waste liquids or removing radioactive components therefrom - Google Patents
Method of decontaminating nuclear power plant waste liquids or removing radioactive components therefromInfo
- Publication number
- CA1154885A CA1154885A CA000372022A CA372022A CA1154885A CA 1154885 A CA1154885 A CA 1154885A CA 000372022 A CA000372022 A CA 000372022A CA 372022 A CA372022 A CA 372022A CA 1154885 A CA1154885 A CA 1154885A
- Authority
- CA
- Canada
- Prior art keywords
- solution
- solid
- solids
- power plant
- 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.)
- Expired
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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Water Treatment By Sorption (AREA)
- Treatment Of Water By Ion Exchange (AREA)
- Removal Of Specific Substances (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
ABSTRACT OF THE DISCLOSURE
A method of decontaminating power plant waste water or removing radioisotopes from liquid power plant wastes com-prises subjecting the liquid waste to preliminary filtration to remove solids therefrom and then directly, or after concentra-tion of the solution, without further solid formation, subject-ing the liquid to ion and isotope exchange with inorganic solids containing metals in the same oxidation state as metal ions in the solution. The solids are then recovered from the solution on an alluvial or deposit filter, the recovered solids being sub-jected to solid waste disposal and the decontaminated liquid, ge-nerally water, being exchanged.
A method of decontaminating power plant waste water or removing radioisotopes from liquid power plant wastes com-prises subjecting the liquid waste to preliminary filtration to remove solids therefrom and then directly, or after concentra-tion of the solution, without further solid formation, subject-ing the liquid to ion and isotope exchange with inorganic solids containing metals in the same oxidation state as metal ions in the solution. The solids are then recovered from the solution on an alluvial or deposit filter, the recovered solids being sub-jected to solid waste disposal and the decontaminated liquid, ge-nerally water, being exchanged.
Description
~ - ~
~S~8~5 The present invention relates to a method of deconta-minating radioactive waste liquids and~ more particularly3 waste water from nuclear power plants. The invention also relates to ~ :
a method of removing radio isotopes in ionic form from radioac-tive liqu~ds and especially power plant waste water~ ~
In the operation of nuclear installations~ waste li - ;
quids are frequently obtained which are radioactive by virtue of the fact that they contain various radi.oactive i50topes in ionlc form. The radio isotopes can include chromium~51~ manganese-54 cobalt 5~ cobalt 60~ iron-55 3 iron-59~ antimony-122~ antimony--124~ tellurium~l23~ zirconium-9$~ niobium~95~ cesium~13~ ce-sium-l37~ strontium-89~ strontium-90~ iodine-1319 neptunium--239 and various uranium and plutoniurn isotopes~
The standard operation of a nuclear electricity-ge nerating power plant1 for example~ may give rise to waste water containing these isotopes among others in a primary coolant or :~ -a secondary coolant while plants for the treatment of nuclear power plant fuels ~ay also give rise to aqueous solutions con-tainin~ such i.sotopes among others.
In order to decontamin~te the waste water~ to reduce the level of radioactivity thereof or remove radio isotopes from the liquid~ the liq~d waste~ according to con~entional techniques~ can be evaporated to dryness or at least to preci-pitate or sediment solids from solution and/or can be treated with substances whlch chemically react wlth the components o~
.. ,: ,.: ..
BS
of the liquid waste to form precipitates which can then bc~
covered~ eOg~ by f~ltration~ and which contain the radionuclides in a solid phase which can be storec3 or disposed of by conven-tional techniques more readily than the bulky liquid waste~
These techniques have been found to give a wide range of decontamination factors~ frequently required complex facilities and operating conditions and are not applicable in many cases for removal of a wide range of contaminantsO As a result~ the waste water decontamination techniques of the prior art are frequently unsatisfactory and inefficient.
It is an object of the present invention to provide an improved method of removing radionuclides from a liquid ra-dioactive waste whereby disadvantages of prior art systems can be obviated.
Another object of the invention is to provide an im-proved method of treating liquid wastes ancl especially waste water frorn nuclear pow~r plants so as to obtain a high decon-tamination factor even where such wastes contain a n~mber o~ -radionuclides~ especially the isotopes mentioned ahove~
Yet an~ther object of the invention is to provide an improved method of removing radioisotopes which are present ln ionic form in a radioactive waste solution from the liquid phase in a particularly inexpenslve ? convenient and ef~icient manner.
- - Here describecl is a method in which the liquid wasteS ~enerally an aque~
ou~ solution of radioactive ca~ions~ is c:onnected wi~h lnorga-~2--~54~8~
nic solids which preferably are insoluble or have ~ low solubi-lity in the liquid phase of the solution but în which the cat-ions have essentially the same oxidation state as cations in so-lution ~ thereby effecting exchange between the cations of the solid and the radionuclides in solution.
Surprisingly~ in spite o~ the fact that the sollds which are used are inorganic compounds which can have~ if de-sired~ low solubility in the treated solution~the ion or iso tope exchange between the radioisotopes in the solution and the nonradioactive cations of corresponding oxidation state in the solid proceeds in a direction which favors the incorporation of the radionuclides in the solids and significantly decontaminates the liquidO
Another surprising phenomenon is that the ion and isotope exchange proceeds with practlcally all radionuclide cat-ions in solution and that practically all concentrations there-. of~ ranging from trace concent~ations to substantial concentra-tions~ are in a well de~ined and reproducible manner so that it is always possible to determlne the degree o~ decontamination obtained with the system ~escrlbed.
` As a result~ the process can b~
used alone to achieve the predictable degree of decontamination andin a~sociation with other radioactive waste treatment methods~ ~
Another advantage is that the soli,~s which are ob- :
tained or the recovered solid-liquid compositions can have es-pecially small volume there~y limiting the total quantlty of the radioactive wastes which may have to be stored in~ fQr ex- ~
ample~ a nuclear power plant facility until final disposal~ In ~.
general~ nuclear power plants have little storage place avail~
able and when large quantities of wastes must be subjected to intermediate storage this space is rapidly consumedO
~5 According to a feature o~ this disclosure, the inorga~
nic solids whichare introduced include one or more of the 9 2 3~ Cr23~ Fe23~ MnO2~ Sb203~ SiO ~ ZrO
Zr3(P04)~ spinels 7 permutites and ~eolites.
The preferred compounds are Cr203 and MnO2~ these having been found to have the best exchanqe capacityO
Naturally~ when the solution contains one or more ra-dionuclides in plurality of different oxidation stages, the so-lids added should include elements in corresponding oxidation states or each of the radionuclides to be exchangedv The system described can be integrated with conventional radioactive waste treatment procedures and it has been found to he advantageous after contacting the solutlon with the solids to col-lect the solids on a deposition-type ilter~ i.e~ by runnlng the slurry onto a ilter material such as filter cloth or paper to obtain a filter cakeO Simple gravity operated ilters can be used or this purpose.
I~he solution may be subjected to a preliminary filtration prior to con-tact with the solids, thereby removing any entrained solids which may originally be presentO ~he solu-tion may then be concentrated by evaporation of water with the concentration terminated before the formation of solids~ i~e.
precipitates or sediments in the solution.
It is also impprtant to know that the contact be-tween the solids and the sol~tion should be suficient to ensure ion and isotope exchange in the manner described so that the sollds do not act solely as ad sorbers or molecular sieves for the radionuclides~
~^4---~C~4~
Specific embodiments of the present invention will now be described, reEerenae being made to the accompa-nying dra~ing~ the sole FIGURE of which is a flow diagram illus-trating the invention~
The process represented by the diagram of the draw-ing recovers at 11 from a nuclear power plant a waste liquid~
generally waste water~ containing a number of radioactive metal ions in solution~ i.eO one or more of the radionuclides men-tioned previously. Any solids entrained with the waste water are removed by preliminary filtration at 12 and delivered at 13 to a solid waste disposal stage 14 which may include container-izing the solid waste and temporary storage thereof awaiting fi-nal disposal by any conventional means.
The filtrate~ i.e. the solution containing the radionuclide ions~ is delivered at 10 to an evaporator 16 which can be heated as represented at 17 indirectly by steaM from the nuclear power plant 10 so that water is evaporated from the so-lution as shown at 26. Evaporation is continued to concentrate the solution in the radionuclide ions but is terminated prior to the sedimentation of solids from solution The concentrate solution is fed to an ion and iso-tope exchange vessel 19 in w~ich the solution is agitated in contact with solids whose metals are in the same oxidation state as the solution metals 3 these solids being metered into a vessel 19 as represented at 20. When the desired isotope and ion exchange is complete~ the resulting slurry is removed at 21 and subjected to gravita~ion filtration on the appro-priate filter medium at 22~ the decontaminated water being di~
54~385 charged at 2~ for further processiny i~ desired while the radio-active solids are recovered at 24 and undergo solid waste dis-posal as described at 250 Specific Example A nuclear power plant waste water containing rela-tive large quantities of the activation products Cr-51~ Mn-54 Co-58~60~ Fe-55~59~ Sb-122/124~125~ Te-123~ Ze-95 and Nb-95;
small amounts of the fission products Cs-134/13'~ Sr~89~90 and I-131; and traces of Np-239 and uranium and plutoniurn isotopes (hot particles) was initially filtered and then concentrated to a point just prior to solids formation.
The waste water concentrate is then agitated with s~
veral g/m MnO2. In a short time~ radionuclides exchanged ap-parently in a relationship corresponding to 54Mn + MnO2 ~ 54MnO2 ~ Mn or 54Mn(~4) ~ MnO2 ~ 54MnO2 ~ Mn(~4) The MnO2 was then separated on a deposition filter and was stored conveniently~ The decontamination factor of the water was 200.
When each of the other solids listed above was si-milarly tested~ ion and isotope exchange was found to be effec-ted and the decontamination factor was increased greatly by the use of a mixture of solids with Cr2O3 and MnO2 predorninating~
The pick-up of manganese and chromium radionuclides by the latter solids was found to be based upon the oxidatlon state of the manganese and chromium in the solids with the man-yanese and chrornium radioisotopes in a solution.
~S~8~5 The present invention relates to a method of deconta-minating radioactive waste liquids and~ more particularly3 waste water from nuclear power plants. The invention also relates to ~ :
a method of removing radio isotopes in ionic form from radioac-tive liqu~ds and especially power plant waste water~ ~
In the operation of nuclear installations~ waste li - ;
quids are frequently obtained which are radioactive by virtue of the fact that they contain various radi.oactive i50topes in ionlc form. The radio isotopes can include chromium~51~ manganese-54 cobalt 5~ cobalt 60~ iron-55 3 iron-59~ antimony-122~ antimony--124~ tellurium~l23~ zirconium-9$~ niobium~95~ cesium~13~ ce-sium-l37~ strontium-89~ strontium-90~ iodine-1319 neptunium--239 and various uranium and plutoniurn isotopes~
The standard operation of a nuclear electricity-ge nerating power plant1 for example~ may give rise to waste water containing these isotopes among others in a primary coolant or :~ -a secondary coolant while plants for the treatment of nuclear power plant fuels ~ay also give rise to aqueous solutions con-tainin~ such i.sotopes among others.
In order to decontamin~te the waste water~ to reduce the level of radioactivity thereof or remove radio isotopes from the liquid~ the liq~d waste~ according to con~entional techniques~ can be evaporated to dryness or at least to preci-pitate or sediment solids from solution and/or can be treated with substances whlch chemically react wlth the components o~
.. ,: ,.: ..
BS
of the liquid waste to form precipitates which can then bc~
covered~ eOg~ by f~ltration~ and which contain the radionuclides in a solid phase which can be storec3 or disposed of by conven-tional techniques more readily than the bulky liquid waste~
These techniques have been found to give a wide range of decontamination factors~ frequently required complex facilities and operating conditions and are not applicable in many cases for removal of a wide range of contaminantsO As a result~ the waste water decontamination techniques of the prior art are frequently unsatisfactory and inefficient.
It is an object of the present invention to provide an improved method of removing radionuclides from a liquid ra-dioactive waste whereby disadvantages of prior art systems can be obviated.
Another object of the invention is to provide an im-proved method of treating liquid wastes ancl especially waste water frorn nuclear pow~r plants so as to obtain a high decon-tamination factor even where such wastes contain a n~mber o~ -radionuclides~ especially the isotopes mentioned ahove~
Yet an~ther object of the invention is to provide an improved method of removing radioisotopes which are present ln ionic form in a radioactive waste solution from the liquid phase in a particularly inexpenslve ? convenient and ef~icient manner.
- - Here describecl is a method in which the liquid wasteS ~enerally an aque~
ou~ solution of radioactive ca~ions~ is c:onnected wi~h lnorga-~2--~54~8~
nic solids which preferably are insoluble or have ~ low solubi-lity in the liquid phase of the solution but în which the cat-ions have essentially the same oxidation state as cations in so-lution ~ thereby effecting exchange between the cations of the solid and the radionuclides in solution.
Surprisingly~ in spite o~ the fact that the sollds which are used are inorganic compounds which can have~ if de-sired~ low solubility in the treated solution~the ion or iso tope exchange between the radioisotopes in the solution and the nonradioactive cations of corresponding oxidation state in the solid proceeds in a direction which favors the incorporation of the radionuclides in the solids and significantly decontaminates the liquidO
Another surprising phenomenon is that the ion and isotope exchange proceeds with practlcally all radionuclide cat-ions in solution and that practically all concentrations there-. of~ ranging from trace concent~ations to substantial concentra-tions~ are in a well de~ined and reproducible manner so that it is always possible to determlne the degree o~ decontamination obtained with the system ~escrlbed.
` As a result~ the process can b~
used alone to achieve the predictable degree of decontamination andin a~sociation with other radioactive waste treatment methods~ ~
Another advantage is that the soli,~s which are ob- :
tained or the recovered solid-liquid compositions can have es-pecially small volume there~y limiting the total quantlty of the radioactive wastes which may have to be stored in~ fQr ex- ~
ample~ a nuclear power plant facility until final disposal~ In ~.
general~ nuclear power plants have little storage place avail~
able and when large quantities of wastes must be subjected to intermediate storage this space is rapidly consumedO
~5 According to a feature o~ this disclosure, the inorga~
nic solids whichare introduced include one or more of the 9 2 3~ Cr23~ Fe23~ MnO2~ Sb203~ SiO ~ ZrO
Zr3(P04)~ spinels 7 permutites and ~eolites.
The preferred compounds are Cr203 and MnO2~ these having been found to have the best exchanqe capacityO
Naturally~ when the solution contains one or more ra-dionuclides in plurality of different oxidation stages, the so-lids added should include elements in corresponding oxidation states or each of the radionuclides to be exchangedv The system described can be integrated with conventional radioactive waste treatment procedures and it has been found to he advantageous after contacting the solutlon with the solids to col-lect the solids on a deposition-type ilter~ i.e~ by runnlng the slurry onto a ilter material such as filter cloth or paper to obtain a filter cakeO Simple gravity operated ilters can be used or this purpose.
I~he solution may be subjected to a preliminary filtration prior to con-tact with the solids, thereby removing any entrained solids which may originally be presentO ~he solu-tion may then be concentrated by evaporation of water with the concentration terminated before the formation of solids~ i~e.
precipitates or sediments in the solution.
It is also impprtant to know that the contact be-tween the solids and the sol~tion should be suficient to ensure ion and isotope exchange in the manner described so that the sollds do not act solely as ad sorbers or molecular sieves for the radionuclides~
~^4---~C~4~
Specific embodiments of the present invention will now be described, reEerenae being made to the accompa-nying dra~ing~ the sole FIGURE of which is a flow diagram illus-trating the invention~
The process represented by the diagram of the draw-ing recovers at 11 from a nuclear power plant a waste liquid~
generally waste water~ containing a number of radioactive metal ions in solution~ i.eO one or more of the radionuclides men-tioned previously. Any solids entrained with the waste water are removed by preliminary filtration at 12 and delivered at 13 to a solid waste disposal stage 14 which may include container-izing the solid waste and temporary storage thereof awaiting fi-nal disposal by any conventional means.
The filtrate~ i.e. the solution containing the radionuclide ions~ is delivered at 10 to an evaporator 16 which can be heated as represented at 17 indirectly by steaM from the nuclear power plant 10 so that water is evaporated from the so-lution as shown at 26. Evaporation is continued to concentrate the solution in the radionuclide ions but is terminated prior to the sedimentation of solids from solution The concentrate solution is fed to an ion and iso-tope exchange vessel 19 in w~ich the solution is agitated in contact with solids whose metals are in the same oxidation state as the solution metals 3 these solids being metered into a vessel 19 as represented at 20. When the desired isotope and ion exchange is complete~ the resulting slurry is removed at 21 and subjected to gravita~ion filtration on the appro-priate filter medium at 22~ the decontaminated water being di~
54~385 charged at 2~ for further processiny i~ desired while the radio-active solids are recovered at 24 and undergo solid waste dis-posal as described at 250 Specific Example A nuclear power plant waste water containing rela-tive large quantities of the activation products Cr-51~ Mn-54 Co-58~60~ Fe-55~59~ Sb-122/124~125~ Te-123~ Ze-95 and Nb-95;
small amounts of the fission products Cs-134/13'~ Sr~89~90 and I-131; and traces of Np-239 and uranium and plutoniurn isotopes (hot particles) was initially filtered and then concentrated to a point just prior to solids formation.
The waste water concentrate is then agitated with s~
veral g/m MnO2. In a short time~ radionuclides exchanged ap-parently in a relationship corresponding to 54Mn + MnO2 ~ 54MnO2 ~ Mn or 54Mn(~4) ~ MnO2 ~ 54MnO2 ~ Mn(~4) The MnO2 was then separated on a deposition filter and was stored conveniently~ The decontamination factor of the water was 200.
When each of the other solids listed above was si-milarly tested~ ion and isotope exchange was found to be effec-ted and the decontamination factor was increased greatly by the use of a mixture of solids with Cr2O3 and MnO2 predorninating~
The pick-up of manganese and chromium radionuclides by the latter solids was found to be based upon the oxidatlon state of the manganese and chromium in the solids with the man-yanese and chrornium radioisotopes in a solution.
Claims (5)
PROPERTY OR PRIVILEGE IS CLAIMED ARE DEFINED AS FOLLOWS:
1. A method of treating a radioactive waste liquid containing radionuclide cations in a solution which comprises the steps of contacting said solution with at least one non-radioactive inorganic solid having a metal ion of the same oxi-dation state as a radionuclide in the solution to effect ion and isotope exchange between said solution and said solid; said solid being selected from the group which consists of Al2O3, Cr2O3, Fe2O3, MnO2, Sb2O3, SiO2, ZrO2, Zr3(PO4)4, spinels, permutites and zeolites;
and thereafter separating said solid from said solution.
and thereafter separating said solid from said solution.
2. The method defined in claim 1 wherein said solution is an aqueous solution and said solid is substantially insoluble in said solution.
3. The method defined in claim 1, further comprising the step of concentrating the solution prior to contacting the solution with said solid.
4. The method defined in claim 1, further comprising the step of filtering said solution prior to contacting the solution with said solid.
5. The method defined in claim 1 wherein the solid is separated from the solution by filtration.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DEP3007716.8-33 | 1980-02-29 | ||
| DE19803007716 DE3007716A1 (en) | 1980-02-29 | 1980-02-29 | METHOD FOR TREATING WASTE LIQUIDS CONTAINING RADIONUCLIDE FROM NUCLEAR POWER PLANTS OR THE LIKE. |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1154885A true CA1154885A (en) | 1983-10-04 |
Family
ID=6095907
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA000372022A Expired CA1154885A (en) | 1980-02-29 | 1981-02-27 | Method of decontaminating nuclear power plant waste liquids or removing radioactive components therefrom |
Country Status (9)
| Country | Link |
|---|---|
| JP (1) | JPS56137200A (en) |
| BE (1) | BE887710A (en) |
| BR (1) | BR8101179A (en) |
| CA (1) | CA1154885A (en) |
| DE (1) | DE3007716A1 (en) |
| FI (1) | FI810445L (en) |
| FR (1) | FR2478364A1 (en) |
| NL (1) | NL8100649A (en) |
| SE (1) | SE8100553L (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| AU668589B2 (en) * | 1991-05-16 | 1996-05-09 | Jci Limited | A method of treating water containing radioactive constituents |
| US9527756B2 (en) | 2012-03-20 | 2016-12-27 | Areva Gmbh | Process for removal of radioactive contamination from wastewater |
Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4737316A (en) * | 1982-11-24 | 1988-04-12 | Pedro B. Macedo | Purification of contaminated liquid |
| US4591455A (en) * | 1982-11-24 | 1986-05-27 | Pedro B. Macedo | Purification of contaminated liquid |
| DE3602591A1 (en) * | 1986-01-29 | 1987-07-30 | Kernforschungsz Karlsruhe | METHOD FOR IMPROVING THE EFFECTIVENESS OF DECONTAMINATING A CORE FUEL AND / OR FUEL SOLUTION OF ZIRCONIUM |
| GB8625656D0 (en) * | 1986-10-27 | 1986-11-26 | British Nuclear Fuels Plc | Inorganic ion exchange material |
| DE3744699A1 (en) * | 1987-02-10 | 1988-12-08 | Allgaeuer Alpenmilch | Process for removing radioactive metal isotopes from liquid foodstuffs or feedstuffs |
| DE4423398A1 (en) * | 1994-07-04 | 1996-01-11 | Siemens Ag | Method and device for disposing of a cation exchanger |
| FR2927725B1 (en) | 2008-02-18 | 2014-09-05 | Commissariat Energie Atomique | PROCESS FOR DECONTAMINATING A LIQUID EFFLUENT IN ONE OR MORE CHEMICAL ELEMENTS BY SOLID-LIQUID EXTRACTION UTILIZING A RECYCLING LOOP |
| JP6672990B2 (en) * | 2016-04-22 | 2020-03-25 | ユニオン昭和株式会社 | Radioactive neptunium decontamination agent |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3167504A (en) * | 1961-10-04 | 1965-01-26 | Minerals & Chem Philipp Corp | Method for purifying radioactive waste liquid |
| US4087375A (en) * | 1975-05-07 | 1978-05-02 | Shin Tohoku Chemical Industry Co., Ltd. | Method for treating radioactive waste water |
| BE859028A (en) * | 1977-09-26 | 1978-03-28 | Belgonucleaire Sa | WATER DECONTAMINATION PROCESS |
-
1980
- 1980-02-29 DE DE19803007716 patent/DE3007716A1/en not_active Ceased
-
1981
- 1981-01-28 SE SE8100553A patent/SE8100553L/en not_active Application Discontinuation
- 1981-02-11 NL NL8100649A patent/NL8100649A/en not_active Application Discontinuation
- 1981-02-13 FI FI810445A patent/FI810445L/en not_active Application Discontinuation
- 1981-02-23 JP JP2439781A patent/JPS56137200A/en active Pending
- 1981-02-26 BR BR8101179A patent/BR8101179A/en not_active IP Right Cessation
- 1981-02-26 FR FR8103825A patent/FR2478364A1/en not_active Withdrawn
- 1981-02-27 CA CA000372022A patent/CA1154885A/en not_active Expired
- 1981-02-27 BE BE2/59028A patent/BE887710A/en unknown
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| AU668589B2 (en) * | 1991-05-16 | 1996-05-09 | Jci Limited | A method of treating water containing radioactive constituents |
| US9527756B2 (en) | 2012-03-20 | 2016-12-27 | Areva Gmbh | Process for removal of radioactive contamination from wastewater |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS56137200A (en) | 1981-10-26 |
| FI810445L (en) | 1981-08-30 |
| SE8100553L (en) | 1981-08-30 |
| FR2478364A1 (en) | 1981-09-18 |
| DE3007716A1 (en) | 1981-09-10 |
| BE887710A (en) | 1981-06-15 |
| NL8100649A (en) | 1981-10-01 |
| BR8101179A (en) | 1981-09-01 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| MKEX | Expiry |