US3679595A - Method of concentrating radioactive waste - Google Patents
Method of concentrating radioactive waste Download PDFInfo
- Publication number
- US3679595A US3679595A US834866A US3679595DA US3679595A US 3679595 A US3679595 A US 3679595A US 834866 A US834866 A US 834866A US 3679595D A US3679595D A US 3679595DA US 3679595 A US3679595 A US 3679595A
- Authority
- US
- United States
- Prior art keywords
- radioactive waste
- concentrate
- added
- bone glue
- dust
- 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
- 238000000034 method Methods 0.000 title abstract description 18
- 239000002901 radioactive waste Substances 0.000 title abstract description 9
- 239000002639 bone cement Substances 0.000 abstract description 12
- 239000012141 concentrate Substances 0.000 abstract description 11
- 239000007787 solid Substances 0.000 abstract description 10
- 238000001035 drying Methods 0.000 abstract description 9
- 229920000867 polyelectrolyte Polymers 0.000 abstract description 5
- 230000015572 biosynthetic process Effects 0.000 abstract description 4
- 230000008719 thickening Effects 0.000 abstract description 4
- 239000000725 suspension Substances 0.000 abstract 1
- 239000000126 substance Substances 0.000 description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 239000000428 dust Substances 0.000 description 6
- 229920002401 polyacrylamide Polymers 0.000 description 4
- 230000005855 radiation Effects 0.000 description 4
- 239000007864 aqueous solution Substances 0.000 description 3
- 239000007900 aqueous suspension Substances 0.000 description 3
- 239000010426 asphalt Substances 0.000 description 3
- 239000011343 solid material Substances 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 239000004568 cement Substances 0.000 description 2
- 230000008020 evaporation Effects 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 239000003292 glue Substances 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- 239000002351 wastewater Substances 0.000 description 2
- 108010010803 Gelatin Proteins 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 238000002425 crystallisation Methods 0.000 description 1
- 230000008025 crystallization Effects 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 229920000159 gelatin Polymers 0.000 description 1
- 239000008273 gelatin Substances 0.000 description 1
- 235000019322 gelatine Nutrition 0.000 description 1
- 235000011852 gelatine desserts Nutrition 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 230000006698 induction Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 238000003825 pressing Methods 0.000 description 1
- 230000002285 radioactive effect Effects 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
- G21F9/08—Processing by evaporation; by distillation
-
- 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
- G21F9/16—Processing by fixation in stable solid media
- G21F9/167—Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tars
Definitions
- the method is characterized in that the concentrate is dried on heated rollers, whereby a polyelectrolyte is added, in a known manner, for the purpose of adjusting an appropriate viscosity. Bone glue is added, in order to prevent formation of dust and as an embedding mass. The rolled product is subsequently compressed into solid bodies.
- the present invention relates to a method for concentrating aqueous solutions and suspensions of radioactive waste by thickening and drying. It is known to concentrate such liquids up to a solid content to 10 to 15%. This concentrate is bound by being mixed with cement or hot bitumen or asphalt and stored in standard 200 liter barrels, in collecting places. The content of such a storage barrel containing radioactive waste, is virtually not determined at the barrel wall by the highly permeable radiation of 200 mr./h., but by the applied storage technique. The bitumizing is associated with a very large expenditure, with regard to machinery, and permits the embedding of a maximum of 60% by weight of solid materials. During a simple cementing process, a maximum of only by weight of solid materials can be included.
- This method makes it possible to bind up to 70% by weight of solid substances.
- a conventional bone glue or gelatin is added to the concentrate, produced in the customary manner. There is no danger that the bone glue may precipitate, since pH values of 2-3 must be adjusted for the evaporation.
- a very important advantage of using bone glue consists in the fact that the latter is viscous at temperatures required for drying, so that dust will be reliably prevented.
- Another advantage associated with bone glue is the fact that the latter has great radiation resistance, being an albumen substance. Its softening point depends on its water content and can therefore be simply adjusted as to be compressible for the purpose of reducing the volume. It binds 12 to 14% water, similarly to water of crystallization. When the actual value deviates therefrom, the water is bound or free.
- the drying of the concentrate is preferably carried out on a rolled dryer.
- the viscosity must be so altered, by admixing polyacrylamide, that an adequate film can be obtained on the drying roller.
- the residual moisture which is desired for the compression process that forms solid bodies, can be obtained directly on the roller or during a subsequent drying process.
- a process for concentrating aqueous solutions and suspensions of radioactive waste by thickening and drying which comprises adding a polyelectrolyte to adjust the viscosity, adding bone glue to prevent formation of dust and to form an embedding mass, drying the concentrate on heated rollers and compressing the rolled product into solid bodies.
- polyacrylamide is the polyelectrolyte.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
- Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
- Heat Treatment Of Water, Waste Water Or Sewage (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19681764586 DE1764586B1 (de) | 1968-06-29 | 1968-06-29 | Verfahren zur konzentrierung radioaktiver abfaelle |
Publications (1)
Publication Number | Publication Date |
---|---|
US3679595A true US3679595A (en) | 1972-07-25 |
Family
ID=5698046
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US834866A Expired - Lifetime US3679595A (en) | 1968-06-29 | 1969-06-19 | Method of concentrating radioactive waste |
Country Status (10)
Country | Link |
---|---|
US (1) | US3679595A (fr) |
JP (1) | JPS4838679B1 (fr) |
AT (1) | AT326781B (fr) |
BE (1) | BE735154A (fr) |
BR (1) | BR6910254D0 (fr) |
CH (1) | CH489096A (fr) |
DE (1) | DE1764586B1 (fr) |
ES (1) | ES368913A1 (fr) |
FR (1) | FR2014435A1 (fr) |
GB (1) | GB1242665A (fr) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4122028A (en) * | 1976-01-28 | 1978-10-24 | Nukem Nuklear-Chemie Und Metallurgie Gmbh | Process for solidifying and eliminating radioactive borate containing liquids |
US4148745A (en) * | 1973-06-16 | 1979-04-10 | Gesellschaft Fur Kernforschung M.B.H. | Method of preparing phosphoric acid esters for non-polluting storage by incorporation in polyvinyl chloride |
US4234448A (en) * | 1976-11-01 | 1980-11-18 | Hitachi, Ltd. | Method and apparatus for treating radioactive waste |
US4762647A (en) * | 1985-06-12 | 1988-08-09 | Westinghouse Electric Corp. | Ion exchange resin volume reduction |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE755971R (fr) * | 1969-10-11 | 1971-02-15 | Siemens Ag | Procede de concentration de dechets |
JPS5475000A (en) * | 1977-11-28 | 1979-06-15 | Hitachi Ltd | Method of treating radioactive waste |
DE2944302C2 (de) * | 1979-11-02 | 1985-10-03 | Kraftwerk Union AG, 4330 Mülheim | Verfahren und Einrichtung zum Trocknen von radioaktiven Abwasserkonzentraten mit Borsalzen aus Verdampferanlagen von Kernreaktoren |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB986763A (en) * | 1961-11-15 | 1965-03-24 | Coal Tar Res Ass | Fluid sampling device |
-
1968
- 1968-06-29 DE DE19681764586 patent/DE1764586B1/de not_active Withdrawn
-
1969
- 1969-04-17 AT AT370069A patent/AT326781B/de not_active IP Right Cessation
- 1969-04-24 CH CH631069A patent/CH489096A/de not_active IP Right Cessation
- 1969-06-19 US US834866A patent/US3679595A/en not_active Expired - Lifetime
- 1969-06-25 GB GB32189/69A patent/GB1242665A/en not_active Expired
- 1969-06-25 BE BE735154D patent/BE735154A/xx unknown
- 1969-06-26 FR FR6921576A patent/FR2014435A1/fr not_active Withdrawn
- 1969-06-27 BR BR210254/69A patent/BR6910254D0/pt unknown
- 1969-06-28 ES ES368913A patent/ES368913A1/es not_active Expired
- 1969-06-30 JP JP44051001A patent/JPS4838679B1/ja active Pending
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4148745A (en) * | 1973-06-16 | 1979-04-10 | Gesellschaft Fur Kernforschung M.B.H. | Method of preparing phosphoric acid esters for non-polluting storage by incorporation in polyvinyl chloride |
US4122028A (en) * | 1976-01-28 | 1978-10-24 | Nukem Nuklear-Chemie Und Metallurgie Gmbh | Process for solidifying and eliminating radioactive borate containing liquids |
US4234448A (en) * | 1976-11-01 | 1980-11-18 | Hitachi, Ltd. | Method and apparatus for treating radioactive waste |
US4762647A (en) * | 1985-06-12 | 1988-08-09 | Westinghouse Electric Corp. | Ion exchange resin volume reduction |
Also Published As
Publication number | Publication date |
---|---|
DE1764586B1 (de) | 1971-07-15 |
JPS4838679B1 (fr) | 1973-11-19 |
ATA370069A (de) | 1975-03-15 |
BR6910254D0 (pt) | 1973-01-11 |
CH489096A (de) | 1970-04-15 |
ES368913A1 (es) | 1971-05-01 |
GB1242665A (en) | 1971-08-11 |
BE735154A (fr) | 1969-12-01 |
FR2014435A1 (fr) | 1970-04-17 |
AT326781B (de) | 1975-12-29 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US3679595A (en) | Method of concentrating radioactive waste | |
US4122028A (en) | Process for solidifying and eliminating radioactive borate containing liquids | |
GB1529510A (en) | Embedding radioactive and/or toxic solid matter | |
DE1082993B (de) | Verfahren zum Beseitigen radioaktiver Fluessigkeit | |
JPS6184000A (ja) | 放射性および/または放射能で汚染した固体廃棄物および蒸留濃縮物を最終貯蔵容器に最終貯蔵するための処理方法 | |
EP0028726B1 (fr) | Procédé et dispositif pour sécher les concentrés radioactifs provenant des installations d'évaporation | |
US4500449A (en) | Method for solidifying boron-containing radioactive residues | |
SU501682A3 (ru) | Способ захоронени радиоактивных или токсичных веществ | |
GB1564878A (en) | Method of improving the leaching resistance of solidified bitumen products containing radioactive substances | |
FR2445590A3 (fr) | Conteneur de transport perdu en beton, destine a recevoir un fut a contenu radioactif | |
ES449844A1 (es) | Procedimiento y dispositivo para eliminar desperdicios de material sintetico radiantes. | |
EP0088512B1 (fr) | Procédé pour solidifier des déchets | |
Sinha et al. | Fixation of radioactive chemical sludge in a matrix containing cement and additives | |
DE1764586C (de) | Verfahren zur Konzentrierung radioaktiver Abfalle | |
US2745546A (en) | Treating packing material | |
FI84944C (fi) | Saett att framstaella inkapslat jonbytarharts. | |
SU550040A1 (ru) | Способ переработки радиоактивных отходов путем включени их в битум | |
AT379250B (de) | Einbettungsmasse und verfahren zum einbetten von anionenaustauscherharzen bzw. diese enthaltenden gemischen | |
CA1205097A (fr) | Procede de preparation des dechets en vue d'une elimination non polluante | |
SU479306A3 (ru) | Способ заделки биологически вредных отходов в битум | |
US1938677A (en) | Water treating compound | |
Neilson Jr | Immobilization of wet solid wastes at nuclear power plants | |
JPS5925667A (ja) | 乾海苔製造における調合液濃度調整方法 | |
JPS58186099A (ja) | 放射性廃水の固化処理法 | |
RU2046410C1 (ru) | Способ обработки жидких радиоактивных отходов |