US3716490A - Treatment of radioactive liquids - Google Patents
Treatment of radioactive liquids Download PDFInfo
- Publication number
- US3716490A US3716490A US00830130A US3716490DA US3716490A US 3716490 A US3716490 A US 3716490A US 00830130 A US00830130 A US 00830130A US 3716490D A US3716490D A US 3716490DA US 3716490 A US3716490 A US 3716490A
- Authority
- US
- United States
- Prior art keywords
- bituminous substance
- bituminous
- radioactive
- ion exchange
- substance
- 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 - Lifetime
Links
- 230000002285 radioactive effect Effects 0.000 title abstract description 42
- 239000007788 liquid Substances 0.000 title abstract description 28
- 239000000126 substance Substances 0.000 abstract description 112
- 238000005342 ion exchange Methods 0.000 abstract description 36
- 239000000463 material Substances 0.000 abstract description 33
- 238000000034 method Methods 0.000 abstract description 21
- 239000010426 asphalt Substances 0.000 abstract description 4
- 238000005202 decontamination Methods 0.000 abstract description 4
- 230000003588 decontaminative effect Effects 0.000 abstract description 4
- 230000004927 fusion Effects 0.000 abstract description 4
- 230000006835 compression Effects 0.000 abstract description 3
- 238000007906 compression Methods 0.000 abstract description 3
- 150000002500 ions Chemical class 0.000 description 26
- QAOWNCQODCNURD-UHFFFAOYSA-N sulfuric acid Substances OS(O)(=O)=O QAOWNCQODCNURD-UHFFFAOYSA-N 0.000 description 21
- 239000002245 particle Substances 0.000 description 19
- 238000006277 sulfonation reaction Methods 0.000 description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 14
- 239000000047 product Substances 0.000 description 8
- 239000012857 radioactive material Substances 0.000 description 8
- 239000000203 mixture Substances 0.000 description 7
- 150000001875 compounds Chemical class 0.000 description 5
- 125000004435 hydrogen atom Chemical group [H]* 0.000 description 5
- 238000002844 melting Methods 0.000 description 5
- 230000008018 melting Effects 0.000 description 5
- 230000035515 penetration Effects 0.000 description 5
- 239000002699 waste material Substances 0.000 description 5
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 4
- 238000006243 chemical reaction Methods 0.000 description 4
- 239000003456 ion exchange resin Substances 0.000 description 4
- 229920003303 ion-exchange polymer Polymers 0.000 description 4
- 239000002244 precipitate Substances 0.000 description 4
- 238000002360 preparation method Methods 0.000 description 4
- 230000035484 reaction time Effects 0.000 description 4
- 239000011575 calcium Substances 0.000 description 3
- 238000000354 decomposition reaction Methods 0.000 description 3
- 238000011038 discontinuous diafiltration by volume reduction Methods 0.000 description 3
- 239000007789 gas Substances 0.000 description 3
- 238000002156 mixing Methods 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 238000003756 stirring Methods 0.000 description 3
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 2
- OYPRJOBELJOOCE-UHFFFAOYSA-N Calcium Chemical compound [Ca] OYPRJOBELJOOCE-UHFFFAOYSA-N 0.000 description 2
- KCXVZYZYPLLWCC-UHFFFAOYSA-N EDTA Chemical compound OC(=O)CN(CC(O)=O)CCN(CC(O)=O)CC(O)=O KCXVZYZYPLLWCC-UHFFFAOYSA-N 0.000 description 2
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 2
- 229910052791 calcium Inorganic materials 0.000 description 2
- 150000001768 cations Chemical class 0.000 description 2
- 238000000975 co-precipitation Methods 0.000 description 2
- 238000005056 compaction Methods 0.000 description 2
- 238000001914 filtration Methods 0.000 description 2
- 230000003100 immobilizing effect Effects 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 239000010808 liquid waste Substances 0.000 description 2
- 239000011777 magnesium Substances 0.000 description 2
- 239000003208 petroleum Substances 0.000 description 2
- 239000002901 radioactive waste Substances 0.000 description 2
- 239000011347 resin Substances 0.000 description 2
- 229920005989 resin Polymers 0.000 description 2
- 239000004852 Asphaltite Substances 0.000 description 1
- FYYHWMGAXLPEAU-UHFFFAOYSA-N Magnesium Chemical compound [Mg] FYYHWMGAXLPEAU-UHFFFAOYSA-N 0.000 description 1
- 229910000831 Steel Inorganic materials 0.000 description 1
- 229910001424 calcium ion Inorganic materials 0.000 description 1
- 239000003054 catalyst Substances 0.000 description 1
- 150000001805 chlorine compounds Chemical class 0.000 description 1
- 230000000536 complexating effect Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 238000004821 distillation Methods 0.000 description 1
- VFNGKCDDZUSWLR-UHFFFAOYSA-N disulfuric acid Chemical compound OS(=O)(=O)OS(O)(=O)=O VFNGKCDDZUSWLR-UHFFFAOYSA-N 0.000 description 1
- 229960001484 edetic acid Drugs 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000839 emulsion Substances 0.000 description 1
- 238000005538 encapsulation Methods 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 238000002386 leaching Methods 0.000 description 1
- 238000011068 loading method Methods 0.000 description 1
- 229910052749 magnesium Inorganic materials 0.000 description 1
- 229910001425 magnesium ion Inorganic materials 0.000 description 1
- 239000011159 matrix material Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 230000000704 physical effect Effects 0.000 description 1
- 229920001467 poly(styrenesulfonates) Polymers 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000000700 radioactive tracer Substances 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000001172 regenerating effect Effects 0.000 description 1
- 239000011369 resultant mixture Substances 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- YPNVIBVEFVRZPJ-UHFFFAOYSA-L silver sulfate Chemical compound [Ag+].[Ag+].[O-]S([O-])(=O)=O YPNVIBVEFVRZPJ-UHFFFAOYSA-L 0.000 description 1
- 229910000367 silver sulfate Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011780 sodium chloride Substances 0.000 description 1
- 229910001415 sodium ion Inorganic materials 0.000 description 1
- 239000010959 steel Substances 0.000 description 1
- 150000003467 sulfuric acid derivatives Chemical class 0.000 description 1
- XTHPWXDJESJLNJ-UHFFFAOYSA-N sulfurochloridic acid Chemical compound OS(Cl)(=O)=O XTHPWXDJESJLNJ-UHFFFAOYSA-N 0.000 description 1
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
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
- B01J—CHEMICAL OR PHYSICAL PROCESSES, e.g. CATALYSIS OR COLLOID CHEMISTRY; THEIR RELEVANT APPARATUS
- B01J39/00—Cation exchange; Use of material as cation exchangers; Treatment of material for improving the cation exchange properties
- B01J39/04—Processes using organic exchangers
- B01J39/05—Processes using organic exchangers in the strongly acidic form
Definitions
- ABSTRACT OF THE DISCLOSURE A method for decontamination of radioactive liquids and the products thereof, including contacting the radioactive liquid with an ion exchange material formed from a bituminous substance, such as asphalt, and thereafter compacting the ion exchange material, as by fusion and/ or compression.
- the liquid is separated from the waste prior to encapsulation.
- separation has heretofore been accomplished by contacting the contaminated liquid with a synthetic polymeric ion exchange resin, such as a sulfonated polystyrene or the like.
- a synthetic polymeric ion exchange resin such as a sulfonated polystyrene or the like.
- Many different ion exchange resins are well known to persons skilled in the art for this purpose.
- Such a treatment unites the ions of the radioactive material from the waste with the ion exchange resin particles by ion exchange and the liquids may then be separated by any desired technique, such as filtering, etc.
- the radioactive ions freed of the liquid portion of the waste can then be separated from the used ion exchange material by regenerating or burning away the latter.
- Another known process for the treatment of radioactive materials in liquids involves chemical coprecipitation of the radioactive ions.
- the precipitate is then filtered and homogeneously mixed in hot bituminous materials, during which step the water evaporates, or the precipitate can also be mixed with bituminous emulsions.
- the mass thus obtained is stored in steel drums.
- chemical coprecipitation gives rise to precipitates which are difiicult to filter and large filtering installations are needed. Filterability can be improved by dehydrating the precipitate by the freeze-thaw method. However, this again adds an additional undesirable step.
- a method for decontaminating radioactive liquids in which the liquid is contacted with an ion exchange material, comprising a partially sulfonated bituminous substance to thereby transfer radioactive ions from the liquid to the ion exchange material by ion exchange.
- the bituminous substance has a relatively high surface area and by subsequently compacting the bituminous substance under the influence of heat to form a relatively low specific surface area, the radioactive ions may be encapsulated in the compacted bituminous substance.
- the present invention provides a method of decontaminating a radioactive liquid in which the liquid is contacted with an ion exchange material, comprising a partly sulfonated, fusible, bituminous substance to thereby transfer radioactive ions from the liquid to the ion exchange material by ion exchange.
- the bituminous substance initially has a relatively high specific surface area and by subsequently melting the bitumin to form a material of relatively low specific surface area, the radioactive ions may be encapsulated in the material of low specific surface area.
- the present invention provides compacted bodies of an ion exchange material, derived from bituminous substances, having at least a portion of its exchangeable ions replaced with radioactive ions.
- the bituminous substance forming the ion exchange material is partially sulfonated prior to its use.
- the compaction of such material may be attained by fusion or by a combination of fusion and compression.
- a bituminous substance is partially sulfonated in a manner such that it will act as an ion exchange material and can be melted without decomposition or loss.
- Radioactive liquids are then contacted with the sulfonated bituminous substance and, after partial saturation with radioactive ions, the bituminous substance may thereafter be melted to bring about compaction.
- the radioactive ions are thus fixed in an unleachable fashion.
- the melting of the partially sulfonated bitumin does not give rise to decomposition of this material or to a loss of radioactive compounds. Its effect is to reduce the bitumin to a compact form of low bulk having a low specific surface area.
- specific surface area when used herein, means the ratio of total surface area to mass; that is to say, the proportion of the bituminous substance that is exposed for interaction with its environment.
- the specific area depends upon the size of the particles utilized. The size, in turn, may be selected by one skilled in the art and is a function of the type of ion exchange material used, the required rate of passage of liquid therethrough, etc. For example, particles with a diameter of 0.25 mm. have a surface area of 0.186 mm. It would be possible to melt these particles, after saturation, to particles with a volume of 1 cm ⁇ having a surface area of 484 mm. A particle with a volume of 1 cm. will contain 122,000 of the 0.25 mm.
- bituminous substance when utilized herein, is meant to include a class of native and pyrogenous substances containing bitumins or pyrobitumins or resembling them in physical properties and of normally solid or liquid consistency.
- asphalts and Allied Substances by Abraham, 3rd edition, 1932, D. Van Nostrand & 00., pp. 28 through 32 which is adopted herein.
- bituminous substances as ion exchange materials. These sulfonated bituminous substances have heretofore been prepared by treating the bituminous substance with concentrated sulfuric acid at high temperatures, the resulting bituminous ion exchange material being carbonized and infusible.
- fusible bituminous substances can be prepared in one of several alternate ways.
- the bituminous substance may be treated with 80;, compounds in a preselected con centration, for a preselected time and at a predetermined temperature, such that the sulfonation reaction is incomplete.
- a sulfonation reaction may comprise treatment of the bituminous substance for a period of not more than 10 minutes with S compounds in a ratio of about 5 to 20 equivalents of S0 per kilogram of bituminous substance and at a temperature between about 50 C. and 120 C.
- the temperature selected is, of course, dependent upon the softening point of the bituminous substance. For example, if the bituminous substance is very hard, the sulfonation temperatuer must be high.
- a metal salt e.g., sulfates and chlorides
- Suitable 80;; compounds include sulfuric acid, sulfuric acid anhydride, chlorsulfonic acid, etc.
- the temperature to which the bitumin is heated for the sulfonation depends upon the reactivity, the softening point, and other characteristics of the bituminous substance. Accordingly, in another mode of operation, the ratio of sulfuric acid to bituminous substance can be anywhere between 30 to 240 equivalents of sulfuric acid per kilogram of bitumin.
- the sulfonation period is a function of the temperature. For example, at room temperature, the sulfonation reaction would be complete after about 12 hours while at 50 C., the sulfonation period could be reduced to about 5 minutes. As a specific example, with an acid-to-bituminous substance ratio of 150 equivalents per kilogram and a reaction time of 8 minutes at 140 C., the resulting bitumin would have an ion exchange capacity of about 2.3 equivalents per kilogram.
- the sulfonation reaction is preferably carried out in two steps.
- the first step comprises a low sulfonation, giving a material of more crystalline structure which allows increased contact between the sulfuric acid and the bituminous substance, and the second step then comprises a second sulfonation to the desired product.
- the sulfonated bituminous substance is then dried and can be used as an ion exchange material for the decontamination of radioactive liquids. After the bituminous substance has been contacted with the radioactive liquid, the bituminous substance is melted to reduce its overall volume and specific surface area and the radioactive prod ucts are thereby fixed in the bituminous substance in an unleachable manner.
- a partially sulfonated, fusible, bituminous substance can also be prepared by mixing a partially sulfonated, infusible, bituminous substance with fresh bituminous substance (not sulfonated). By choice of suitable proportions of these two components, it is possible to obtain a good structure and excellent fusibility of the ion exchange material.
- the partially sulfonated bituminous substance can be used as an ion exchange material in its hydrogen form, as it is obtained from the sulfonation reaction, or the hydrogen form may be treated with sodium ions (for example, sodium chloride) and then used in the sodium for or even in another appropriate ionic form.
- sodium ions for example, sodium chloride
- the partially sulfonated, bituminous substance may be substantially infusible but sticky and able to be compressed into a clump when heated.
- bituminous substance will not ordinarily be melted until complete saturation with radioactive ions.
- melting of the partially saturated bituminous substance is also to be considered within the scope of the present invention.
- the bituminous substance can be used in granular or powder form, or as a sponge, thin sheets or strips, in a conventional installation for ion exchange materials.
- Penetration refers to a. measure of the consistency of a bituminous substance, expressed as the distance in tenths of a mm. that a standard needle vertically penetrates a sample of the substance under known conditions of loading, time and temperature. Where the test conditions are not specifically mentioned, the load, time and temperature are 100 g., 5 sec., and 25 C., respectively, and the units of penetration or hundredths of a cm. The load is defined as the total moving weight of the needle and attachments. See Asphalts and Allied Substances, Abraham, D. Van Nostrand Co., Third edition, 1929, pp. 664 to 668.
- EXAMPLE 1 Preparation of partially sulfonated, fusible bituminous substance
- bituminous substance obtained by distillation of a crude petroleum oil and having a penetration of 280-320, was heated to a temperature of C. and maintained at this temperature.
- a mixture of 15 equivalents of sulfuric acid and 1 ppm. silver sulfate was added to the hot bituminous substance while stirring the mixture.
- the reaction time was 4 minutes and the product was thereafter poured into cold water.
- the cooled substance thus obtained was ground under water, removed from the water and dried.
- the product comprised a partially sulfonated bituminous substance that was readily fusible at a temperature of about 80 C.
- EXAMPLE 2 Preparation of partially sulfonated, fusible bituminous substance
- One kilogram of the bituminous substance of Example 1 was heated to 140 C. 30 equivalents of sulfuric acid were added while stirring and the reaction was continued for 4 minutes. The product then was poured into cold water. The substance obtainedwas filtered and dried at 80 C. This substance was then re-heated to 140 C. and again sulfonated with 120 equivalents of sulfuric acid. The mixture was stirred during a reaction time of 4 minutes and then poured into cold water, filtered and dried at 80 C. 50% of this sulfonated bituminous substance was then mixed with 50% fresh bituminous substance having a penetration of 280-320. The resultant mixture was washed, dried and ground to particles of about 35 to 65 mesh.
- the sulfonated bituminous substance is not fusible, it can be mixed with fresh (not sulfonated) bituminous substance, as illustrated by the preceding example, in a ratio varying from 80 to 20 parts fresh bituminous substance to 20' to 80 parts sulfonated bituminous substance.
- Such mixtures are readily fusible and have an excellent ion exchange capacity.
- the ion exchange capacity is in a region of 1.5 equivalents per kilogram. It is to be noted that the mixing of sulfonated bituminous substance and fresh bituminous substance gives rise to a very strong sulfonation reaction with the fresh bituminous substance which is accompanied by gas release.
- the fresh and fusible sulfonated bituminous substance must be mixed before ion exchange. If the infusible bituminous substance were mixed with fresh bituminous substance after the ion exchange (which mixing would give a fusible bitumin), the gas release would cause release of the radioactive material.
- EXAMPLE 3 Preparation of partially sulfonated bitumin which is not fusible but may be made so
- One kilogram of bituminous substance having a penetration of 1557 was ground to particle size of 35 mesh. These particles were added to 90 equivalents per kilogram of sulfuric acid at a temperature of about 20 C. Stirring was continued for a reaction time of about 3 hours. The substance obtained was then poured into water and dried at 100 C. The product of this reaction was a partially sulfonated bituminous substance having a good ion exchange capacity but it was infusible. The bituminous substance, however, was sticky and could be compressed after ion exchange to form a clump when heated.
- bituminous substance For the preparation of the bituminous substance in this instance, a hard species of bituminous material must be used.
- the ratio of sulfuric acid to bituminous substance should be between about 30 to 180 equivalents of sulfuric acid per kilogram of bituminous substance.
- the reaction temperature should be in the region of room temperature, i.e., plus or minus 20 C., and the sulfonation time should be about 1 to 12 hours.
- EXAMPLE 4 Treatment of radioactive liquids To water containing 32 ppm. calcium and 4.8 ppm. magnesium, a tracer of Sr was added in amount sufiicient to cause a counting rate of 20 counts/sec./ml. This water was passed through a column containing a bed of particles of partially sulfonated bituminous substance, having a mesh size of 30 to 65 mesh and prepared according to the method of Example 2, at a rate of 30 bed volumes per hour. After 300 bed volumes of water had passed through the column, a breakthrough of 10% Sr was detected.
- the particles of partially sulfonated bitumin were then dried and melted and the ion exchanged radioactive ions were fixed in an unleachable manner in the bituminous substance.
- the melting reduced the volume of the bituminous substance by a factor of 5.
- the total volume reduction factor is thus 1500, i.e., the bituminous substance decontaminated 300 bed volumes of water before stauration and the bituminous particles when melted were reduced to a compact mass of bitumin occupying /5 of the volume occupied by the particles and having a many times lower surface area.
- the volume reduction may be increased by initially complexing some non-radioactive cations in the liquid in such a manner that only the free radioactive cations will take the free places on the ion exchange material.
- EXAMPLE 5 The procedure of Example 4 was repeated with EDTA (ethylenediaminetetracetic acid) added to the radioactive water so that 0.2 meq. calcium/liter of water remained free, i.e., the Mg and Ca ions were complexed with the exception of 0.2 meq. Ca/liter. This water was passed through the column, the 10% breakthrough occurred only after 1600 bed volumes had passed through the column, the total volume reduction being a factor of about 8000.
- EDTA ethylenediaminetetracetic acid
- a method of decontaminating radioactive liquids containing radioactive ions comprising; providing a solid, fusible, partly sulfonated bituminous substance; thereafter contacting said fusible, partially sulfontaed bituminous substance with a liquid waste containing radioactive ions to ion exchange said radioactive ions with the sulfonated portion of said bituminous substance; and finally, melting said bituminous substance to reduce the volume thereof and encapsulate said radioactive ions.
- bituminous substance prepared by treating a bituminous substance for less than 10 minutes with $0 compounds in a ratio of 5 to 20 equivalents SO /kilogram of bituminous substance and at a temperature between 50 C. and C.
- a method as claimed in claim 1 in which the partially sulfonated bituminous substance comprises a mixture of a substantially infusible, partially sulfonated bituminous substance and a non-sulfonated fusible bituminous substance.
- a method of decontaminating radioactive liquids containing radioactive ions comprising; providing a solid, partially sulfonated bituminous substance which is substantially infusible but will cohere when heated; thereafter contacting said bitumen with a liquid waste containing radioactive ions to ion exchange said radioactive ions with the sulfonated portion of said bituminous substance; and finally, compacting said bituminous substance under the influence of heat to reduce the volume thereof and encapsulate said radioactive ions.
- a compacted mass of ion exchange material prepared from a bituminous substance having at least a portion of its exchangeable ions replaced with radioactive ions, said mass of compacted bituminous substance forming a matrix surrounding, encapsulating and immobilizing said radioactive ions whereby the leaching of said radioactive ions from said mass is effectively prevented.
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- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Compositions Of Macromolecular Compounds (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB56172/67A GB1188396A (en) | 1967-12-11 | 1967-12-11 | Treatment of Radioactive Liquids |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| US3716490A true US3716490A (en) | 1973-02-13 |
Family
ID=10475921
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| US00830130A Expired - Lifetime US3716490A (en) | 1967-12-11 | 1969-06-03 | Treatment of radioactive liquids |
Country Status (9)
| Country | Link |
|---|---|
| US (1) | US3716490A (fr) |
| JP (1) | JPS4814480B1 (fr) |
| BE (1) | BE725020A (fr) |
| CH (1) | CH493433A (fr) |
| DE (1) | DE1813708A1 (fr) |
| FR (1) | FR1596839A (fr) |
| GB (1) | GB1188396A (fr) |
| NL (1) | NL6817746A (fr) |
| SE (1) | SE331726B (fr) |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4056112A (en) * | 1974-05-02 | 1977-11-01 | Calvin Calmon | Containment and removal of radioactive spills by depositing a crosslinked ion exchange composition in a dry form over region of spill |
| US4123380A (en) * | 1976-04-02 | 1978-10-31 | Ab Bofors | Waste disposal |
| US4204974A (en) * | 1975-07-15 | 1980-05-27 | Kraftwerk Union Aktiengesellschaft | Method for removing radioactive plastic wastes and apparatus therefor |
| US4252667A (en) * | 1977-07-15 | 1981-02-24 | Kernforschungszentrum Karlsruhe Gmbh | Method for placing radioactive wastes mixed with bitumen into containers |
| US4505888A (en) * | 1983-05-27 | 1985-03-19 | E. I. Du Pont De Nemours & Company | Tracer for circulation determinations |
| WO1987001502A1 (fr) * | 1985-08-30 | 1987-03-12 | Hoeglund Lars Olov | Resine a echange d'ions encapsulee et son procede de fabrication |
| US4663086A (en) * | 1984-03-21 | 1987-05-05 | Commissariat A L'energie Atomique | Process for bituminizing radioactive waste constituted by cation and/or anion exchange resins |
| US4844838A (en) * | 1987-02-13 | 1989-07-04 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Method of treatment of radioactive liquid waste |
| US5055237A (en) * | 1990-08-14 | 1991-10-08 | Technology International Incorporated | Method of compacting low-level radioactive waste utilizing freezing and electrodialyzing concentration processes |
| US5256338A (en) * | 1990-11-28 | 1993-10-26 | Hitachi, Ltd. | Solidifying materials for radioactive waste disposal, structures made of said materials for radioactive waste disposal and process for solidifying of radioactive wastes |
| US5463163A (en) * | 1993-03-29 | 1995-10-31 | Sol-Cap, Inc. | Process for absorbing toxic waste for long term permanent storage |
| US20090069620A1 (en) * | 2004-04-29 | 2009-03-12 | Terry Industries, Inc. | Radiation shields and techniques for radiation shielding |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2134694A (en) * | 1983-01-14 | 1984-08-15 | British Nuclear Fuels Ltd | Improvements in and relating to the treatment of radioactive effluents |
| US4762647A (en) * | 1985-06-12 | 1988-08-09 | Westinghouse Electric Corp. | Ion exchange resin volume reduction |
-
1967
- 1967-12-11 GB GB56172/67A patent/GB1188396A/en not_active Expired
-
1968
- 1968-12-02 CH CH1791768A patent/CH493433A/fr not_active IP Right Cessation
- 1968-12-06 BE BE725020D patent/BE725020A/xx unknown
- 1968-12-09 SE SE16824/68A patent/SE331726B/xx unknown
- 1968-12-10 DE DE19681813708 patent/DE1813708A1/de active Pending
- 1968-12-10 FR FR1596839D patent/FR1596839A/fr not_active Expired
- 1968-12-11 JP JP43090837A patent/JPS4814480B1/ja active Pending
- 1968-12-11 NL NL6817746A patent/NL6817746A/xx unknown
-
1969
- 1969-06-03 US US00830130A patent/US3716490A/en not_active Expired - Lifetime
Cited By (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4056112A (en) * | 1974-05-02 | 1977-11-01 | Calvin Calmon | Containment and removal of radioactive spills by depositing a crosslinked ion exchange composition in a dry form over region of spill |
| US4204974A (en) * | 1975-07-15 | 1980-05-27 | Kraftwerk Union Aktiengesellschaft | Method for removing radioactive plastic wastes and apparatus therefor |
| US4123380A (en) * | 1976-04-02 | 1978-10-31 | Ab Bofors | Waste disposal |
| US4252667A (en) * | 1977-07-15 | 1981-02-24 | Kernforschungszentrum Karlsruhe Gmbh | Method for placing radioactive wastes mixed with bitumen into containers |
| US4505888A (en) * | 1983-05-27 | 1985-03-19 | E. I. Du Pont De Nemours & Company | Tracer for circulation determinations |
| US4663086A (en) * | 1984-03-21 | 1987-05-05 | Commissariat A L'energie Atomique | Process for bituminizing radioactive waste constituted by cation and/or anion exchange resins |
| WO1987001502A1 (fr) * | 1985-08-30 | 1987-03-12 | Hoeglund Lars Olov | Resine a echange d'ions encapsulee et son procede de fabrication |
| US4847006A (en) * | 1985-08-30 | 1989-07-11 | Hoeglund Lars O | Encapsulated ion-exchange resin and a method for its manufacture |
| US4844838A (en) * | 1987-02-13 | 1989-07-04 | Doryokuro Kakunenryo Kaihatsu Jigyodan | Method of treatment of radioactive liquid waste |
| US5055237A (en) * | 1990-08-14 | 1991-10-08 | Technology International Incorporated | Method of compacting low-level radioactive waste utilizing freezing and electrodialyzing concentration processes |
| US5256338A (en) * | 1990-11-28 | 1993-10-26 | Hitachi, Ltd. | Solidifying materials for radioactive waste disposal, structures made of said materials for radioactive waste disposal and process for solidifying of radioactive wastes |
| US5463163A (en) * | 1993-03-29 | 1995-10-31 | Sol-Cap, Inc. | Process for absorbing toxic waste for long term permanent storage |
| US20090069620A1 (en) * | 2004-04-29 | 2009-03-12 | Terry Industries, Inc. | Radiation shields and techniques for radiation shielding |
| US7518028B2 (en) * | 2004-04-29 | 2009-04-14 | Terry Asphalt Materials, Inc. | Radiation shields and techniques for radiation shielding |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS4814480B1 (fr) | 1973-05-08 |
| NL6817746A (fr) | 1969-06-13 |
| DE1813708A1 (de) | 1969-08-28 |
| FR1596839A (fr) | 1970-06-22 |
| SE331726B (fr) | 1971-01-11 |
| BE725020A (fr) | 1969-06-06 |
| GB1188396A (en) | 1970-04-15 |
| CH493433A (fr) | 1970-07-15 |
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