WO1984000440A1 - Method for the treatment of fuel elements after their extraction from a reactor core - Google Patents
Method for the treatment of fuel elements after their extraction from a reactor core Download PDFInfo
- Publication number
- WO1984000440A1 WO1984000440A1 PCT/EP1983/000168 EP8300168W WO8400440A1 WO 1984000440 A1 WO1984000440 A1 WO 1984000440A1 EP 8300168 W EP8300168 W EP 8300168W WO 8400440 A1 WO8400440 A1 WO 8400440A1
- Authority
- WO
- WIPO (PCT)
- Prior art keywords
- pellets
- glass
- denitration
- solution
- stage
- 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.)
- Ceased
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C03—GLASS; MINERAL OR SLAG WOOL
- C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
- C03C1/00—Ingredients generally applicable to manufacture of glasses, glazes, or vitreous enamels
- C03C1/02—Pretreated ingredients
- C03C1/026—Pelletisation or prereacting of powdered raw materials
-
- C—CHEMISTRY; METALLURGY
- C03—GLASS; MINERAL OR SLAG WOOL
- C03C—CHEMICAL COMPOSITION OF GLASSES, GLAZES OR VITREOUS ENAMELS; SURFACE TREATMENT OF GLASS; SURFACE TREATMENT OF FIBRES OR FILAMENTS MADE FROM GLASS, MINERALS OR SLAGS; JOINING GLASS TO GLASS OR OTHER MATERIALS
- C03C1/00—Ingredients generally applicable to manufacture of glasses, glazes, or vitreous enamels
- C03C1/002—Use of waste materials, e.g. slags
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/48—Non-aqueous processes
-
- 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
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
-
- 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
- G21F9/28—Treating solids
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/305—Glass or glass like matrix
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
Definitions
- the invention relates to a process for the preparation of burnt-out fuel elements from nuclear reactors, in which the fuel elements are dissolved in hot nitric acid and the solution, after removal of solid impurities and other reusable uranium and plutonium components, is first subjected to concentration and denitrification as well as the recycling of the processing products.
- the aim of the present invention is to provide a method for processing spent fuel elements or for obtaining otherwise reusable materials from spent fuel elements, the disadvantages of the known methods, namely ⁇ ⁇ the formation of dust and aerosols in the course of the processing method and the adverse consequences resulting therefrom are avoided.
- the invention consists in that the denitrification takes place in several stages for the selective separation of the solution component and the highly active solution component isolated in this way is granulated into pellets.
- the invention provides a refurbishment process for spent fuel elements, with the aid of which the inactive constituents, in particular noble metals, and then the highly active constituents are precipitated and thus separately recovered, and the highly active ones
- Materials are brought into a form that can either be recycled directly or after melting into a glass matrix, or else be further prepared for final storage i -
- the denitrification is advantageously carried out in a first stage with the help of formic acid and after separation of the noble metals precipitated in this way, in particular rhodium and silver, in a second stage with the aid of parafordehyde or oxalic acid for the purpose of reducing the alkali and alkaline earth nitrates .
- the denitration of the second stage when using paraformaldehyde is advantageously carried out in the presence of potassium hydrogen sulfate as a catalyst.
- the solution is advantageously neutralized before the denitrification, with the neutralization advantageously being carried out with the aid of glass-forming alkaline materials in the event that the further processing of the pellets produced is intended by melting into a glass matrix.
- the pelletization can be carried out in such a way that the highly active waste liquid, after separating the inactive noble metal components, is mixed directly with the aid of radioactive neutral filling materials, such as ash or other powdered waste materials, in a ratio such that the water content of the mixture between Is 8 and 15% by weight, whereupon the mixture is subjected to a pelletizing process.
- the highly active solids can be separated from the waste solution after the second denitrification stage and finely ground Glass frit mixed in a ratio of 20:80 and granulated in a conventional manner in a pelletizer.
- the material to be pelletized is advantageously combined with a mineral substance which reacts with water to form a water-insoluble compound, in particular a hydroxide of a metal II.
- a mineral substance which reacts with water to form a water-insoluble compound, in particular a hydroxide of a metal II.
- Main and secondary group of the periodic system intimately mixed in a quantity resulting in a microfilm layer on the material grains, and the mixture thus obtained is then agglomerated in a manner known per se with the addition of pelletizing liquids. In this way, permanently stable pellets can also be obtained from materials which are not themselves pelletizable or which do not adhere in the dry state.
- the pellets produced in this way can be further processed for final storage in such a way that they are melted directly into a low-melting lead alloy.
- the pellets can also be melted into glass or ceramic bodies, it being possible for the pellets introduced into the melting furnace to be added separately as glass frit, if necessary for the glass or ceramic production.
Landscapes
- Chemical & Material Sciences (AREA)
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Life Sciences & Earth Sciences (AREA)
- Organic Chemistry (AREA)
- Geochemistry & Mineralogy (AREA)
- General Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Inorganic Chemistry (AREA)
- Plasma & Fusion (AREA)
- Processing Of Solid Wastes (AREA)
- Manufacture And Refinement Of Metals (AREA)
Abstract
Description
_£ - _ £ -
Verfahren zur Aufbereitung von abgebrannten Brennelementen aus KernreaktorenProcess for processing spent fuel elements from nuclear reactors
Die Erfindung betrifft ein Verfahren zur Aufbereitung von ausge brannten Brennelementen aus Kernreaktoren, bei dem die Brennele mente in heißer Salpetersäure gelöst und die Lösung nach Abtren nung fester Verunreinigungen sowie der anderweit wiederverwend¬ baren Uran- und Plutoniumbestandteile zunächst einer Aufkonzen- trierung und Denitrierung unterworfen wird sowie die Verwertung der Aufbereitungsprodukte.The invention relates to a process for the preparation of burnt-out fuel elements from nuclear reactors, in which the fuel elements are dissolved in hot nitric acid and the solution, after removal of solid impurities and other reusable uranium and plutonium components, is first subjected to concentration and denitrification as well as the recycling of the processing products.
Bei den bekannten Verfahren dieser Art erfolgt im Anschluß an d Denitrierung eine Vortrocknung sowie anschließend eine Kalzinie rung der aus der Lösung ausgefällten und abgetrennten, im wesen lichen von Alkali- und Erdalkalinitraten bestehenden hochradioaktiven Bestandteile, bei die Kalzinierung entweder in einem Fließbettkalzinator oder einem Sprühkalzinator oder einem Dünnschicht- alzenkalzinator be Temperaturen zwischen 400 und 600 C erfolgt. Die Nachteile die ses Aufarbeitungsverfahrens bestehen- insbesondere darin, daß dur die hohen Kalzinierungstemperaturen vor allem bei der SprühkalziIn the known processes of this type, a pre-drying and then a calcination of the precipitated and separated from the solution, consisting of alkali and alkaline earth metal nitrates highly radioactive constituents takes place after d denitration, in the calcination either in a fluidized bed calciner or a spray calciner or a thin film salt calciner at temperatures between 400 and 600 ° C. The disadvantages of this reprocessing process are, in particular, that the high calcining temperatures, especially in the spray calcine
f OMPI nierung, jedoch auch bei den anderen beiden Kalzinierungsverfahr eine starke Staub- und Aerosolbildung auftritt, die einerseits z erheblichen Verdampfungs- und Sublimatioπsverlusten vor allem an den hochaktiven Bestandteilen Gaesium 137 und Rubidium 106 sowie andererseits zu einer erheblichen Belastung der Apparaturen, ins besondere deren Dichtungen und Abgasfilter führt. Die derart kal zinierten, nunmehr in αxidischer Form vorliegenden hochaktiven Materialien werden anschließend in eine Glasmatrix und diese wie derum zur Endlagerung in eine Bleischmelze eingeschmolzen. Ziel der vorliegenden Erfindung ist die Schaffung eines Verfahrens zu Aufbereitung von abgebrannten Brennelementen bzw. zur Gewinnung anderweit wiederverwendbarer Materialien aus abgebrannten Brenn elementen, wobei die Nachteile der bekannten Verfahren, nämlich ■■ die Staub- und Aerosolbildungen im Verlauf des Aufbereitungsver- fahrens und die sich hieraus ergebenden nachteiligen Folgen ver¬ mieden sind. Die Erfindung besteht darin, daß die Denitrierung i mehreren Stufen zur selektiven Abtrennung der Lösungsbestandteil erfolgt und die derart isolierten hochaktiven Lösungsbestandteil zu Pellets granuliert werden.f OMPI nation, but also in the other two calcination processes a strong dust and aerosol formation occurs, which on the one hand z considerable evaporation and sublimation losses especially on the highly active components Gaesium 137 and Rubidium 106 as well as on the other hand to a considerable load on the equipment, especially its seals and Exhaust filter leads. The highly active materials calcined in this way, now in an oxidic form, are then melted into a glass matrix and this in turn melted into a lead melt for final storage. The aim of the present invention is to provide a method for processing spent fuel elements or for obtaining otherwise reusable materials from spent fuel elements, the disadvantages of the known methods, namely ■ ■ the formation of dust and aerosols in the course of the processing method and the adverse consequences resulting therefrom are avoided. The invention consists in that the denitrification takes place in several stages for the selective separation of the solution component and the highly active solution component isolated in this way is granulated into pellets.
Durch die Erfindung ist ein Aufarbeitungsverfahren für abgebran te Brennelemente geschaffen, mit dessen Hilfe zunächst die inak¬ tiven Bestandteile, insbesondere Edelmetalle und anschließend di hochaktiven Bestandteile ausgefällt und damit getrennt zurückgewonnen und die hochaktivenThe invention provides a refurbishment process for spent fuel elements, with the aid of which the inactive constituents, in particular noble metals, and then the highly active constituents are precipitated and thus separately recovered, and the highly active ones
Materialien in eine Form gebracht werden, die entweder eine ande weitige Verwertung direkt oder nach Einschmelzung in eine Glasma trix oder aber auch eine weitere Vorbereitung zur Endlagerung er i -Materials are brought into a form that can either be recycled directly or after melting into a glass matrix, or else be further prepared for final storage i -
möglicht. Eine Kalzinierung der Materialien mit ihren nachtei¬ ligen Auswirkungen ist nicht erforderlich oder kann in einer stark verminderten, die beschriebenen Nachteile vermeidenden F durchgeführt werden. Die Denitrierung erfolgt vorteilhaft in ei ner ersten Stufe mit Hilfe von Ameisensäure und nach Abscheidun der auf diese Weise ausgefällten Edelmetalle, insbesondere Rhute nium und Silber, in einer zweiten Stufe mit Hilfe von Parafor a dehyd oder Oxalsäure zum Zwecke der Reduzierung der Alkali- und Erdalkalinitrate. Hierbei erfolgt die Denitrierung der zweiten Stufe bei Verwendung von Paraformaldehyd vorteilhaft in Anwesen heit von Kaliumhydrogensulfat als Katalysator. Es wird weiterhi vorteilhaft die Lösung vor der Denitrierung neutralisiert, wobe zweckmäßig die Neutralisierung für den Fall, daß die Weiterver¬ arbeitung der hergestellten Pellets durch Einschmelzen in eine Glasmatrix vorgesehen ist, mit Hilfe von glasbildenden alkalisc Materialien erfolgt.possible. A calcination of the materials with their adverse effects is not necessary or can be carried out in a greatly reduced F avoiding the disadvantages described. The denitrification is advantageously carried out in a first stage with the help of formic acid and after separation of the noble metals precipitated in this way, in particular rhodium and silver, in a second stage with the aid of parafordehyde or oxalic acid for the purpose of reducing the alkali and alkaline earth nitrates . Here, the denitration of the second stage when using paraformaldehyde is advantageously carried out in the presence of potassium hydrogen sulfate as a catalyst. The solution is advantageously neutralized before the denitrification, with the neutralization advantageously being carried out with the aid of glass-forming alkaline materials in the event that the further processing of the pellets produced is intended by melting into a glass matrix.
Die Pelletisierung kann in der Weise erfolgen, daß die hochakti Abfa llflüssigkeit nach Abtrennung der nicht aktiven Edelmetall bestandteile unmittelbar mit Hilfe von radioaktiv neutralen Fül materialien, wie Asche oder anderweit pulverförmige Abfallmater alien, in eine Mengenverhältnis gemischt wird, daß der Wasserge halt der Mischung zwischen 8 und 15 Gew.?ό beträgt, worauf die Mischung einem Pelletisiervorgang unterworfen wird. Es können j doch in einer anderen Ausführungsform des Verfahrens der Erfin¬ dung die hochaktiven Feststoffe nach der zweiten Denitrierungs- stufe aus der Abfall-Lösung abgetrennt und mit fein gemahlener Glasfritte im Verhältnis 20:80 gemischt und in an sich bekannter Weise in einer Pelletisiereinrichtung granuliert werden.The pelletization can be carried out in such a way that the highly active waste liquid, after separating the inactive noble metal components, is mixed directly with the aid of radioactive neutral filling materials, such as ash or other powdered waste materials, in a ratio such that the water content of the mixture between Is 8 and 15% by weight, whereupon the mixture is subjected to a pelletizing process. However, in another embodiment of the process of the invention, the highly active solids can be separated from the waste solution after the second denitrification stage and finely ground Glass frit mixed in a ratio of 20:80 and granulated in a conventional manner in a pelletizer.
Sofern es sich bei den eingesetzten Materialien um mit Wasser ni oder nur schwer pelletisierbare oder nach Trocknung wiederum zer fallende Materialien handelt wird vorteilhaft das zu pelletisie- rende Material mit einer mit Wasser zu einer wasserunlöslichen Verbindung umreagierenden mineralischen Substanz, insbesondere e nem Hydroxid eines Metalls der II. Haupt- und Nebengruppe des pe riodischen Systems, in einer eine Mikrofilmschicht auf den Mate¬ rialkörnern ergebenden Menge innig gemischt und die so gewonnene Mischung anschließend unter Zugabe von Pelletisierungsflüssigkei in an sich bekannter Weise agglomeriert. Auf diese Weise können auch aus an sich nicht pelletisierbaren oder in trockenem Zustan nicht klebenden Materialien dauerhaft stabile Pellets gewonnen werden.Insofar as the materials used are water-nellable or materials which are difficult to pelletize or disintegrate again after drying, the material to be pelletized is advantageously combined with a mineral substance which reacts with water to form a water-insoluble compound, in particular a hydroxide of a metal II. Main and secondary group of the periodic system, intimately mixed in a quantity resulting in a microfilm layer on the material grains, and the mixture thus obtained is then agglomerated in a manner known per se with the addition of pelletizing liquids. In this way, permanently stable pellets can also be obtained from materials which are not themselves pelletizable or which do not adhere in the dry state.
Die in dieser Weise hergestellten Pellets können zur Endablageru weiterverarbeitet werden in der Weise, daß sie direkt in eine niedrigschmelzende Bleilegierung eingeschmolzen werden. Es könne jedoch auch die Pellets zu Glas- oder Keramikkörpern aufgeschmol zen werden, wobei den in den Schmelzofen eingebrachten Pellets g gebenenfalls für die Glas- bzw. Keramikherstellung fehlenden Ma¬ terialbestandteile als Glasfritte gesondert zugegeben werden kön nen.The pellets produced in this way can be further processed for final storage in such a way that they are melted directly into a low-melting lead alloy. However, the pellets can also be melted into glass or ceramic bodies, it being possible for the pellets introduced into the melting furnace to be added separately as glass frit, if necessary for the glass or ceramic production.
Es werden auf diese Weise aus den bisher als Abfallmaterialien bIn this way it is b
f OM handelten und als Endlagerungsprodukte erhebliche Probleme be¬ reitenden Brennelementen nicht nur die inaktiven wertvollen Ede Metalle zurückgewonnen, sondern darüber hinaus aus den hochakti ven Materialien Produkte geschaffen, die mit großem Erfolg ande weitig eingesetzt werden können, etwa bei der Hygienisierung vo Klärschlämmen oder Gewinnung von Niedrigtemperaturwärme.f OM acted and as significant disposal problems for fuel assemblies, not only recover the inactive valuable Ede metals, but also create products from the highly active materials that can be widely used with great success, for example in the sanitation of sewage sludge or in the extraction of low-temperature heat .
OMPI OMPI
Claims
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19823225199 DE3225199A1 (en) | 1982-07-06 | 1982-07-06 | METHOD FOR PROCESSING COMBUSED FUEL ELEMENTS FROM CORE REACTORS |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO1984000440A1 true WO1984000440A1 (en) | 1984-02-02 |
Family
ID=6167731
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/EP1983/000168 Ceased WO1984000440A1 (en) | 1982-07-06 | 1983-07-04 | Method for the treatment of fuel elements after their extraction from a reactor core |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP0112875A1 (en) |
| DE (1) | DE3225199A1 (en) |
| WO (1) | WO1984000440A1 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2779974B1 (en) | 1998-06-19 | 2000-07-13 | Commissariat Energie Atomique | PROCESS FOR THE DISSOLUTION OF PLUTONIUM OR A PLUTONIUM ALLOY |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2835555A (en) * | 1953-11-17 | 1958-05-20 | Healy Thomas Victor | Reduction of acidity of nitric acid solutions by use of formaldehyde |
| FR2051704A1 (en) * | 1969-07-11 | 1971-04-09 | Kernforschung Gmbh Ges Fuer | |
| US3603788A (en) * | 1968-05-06 | 1971-09-07 | Floro D Miraldi | Gamma radiation source and method for the treatment of sewage |
| DE2524169A1 (en) * | 1975-05-31 | 1976-12-23 | Europaeische Ges Fuer Die Chem | High activity radioactive waste stabilised as solid - of active glass granulate embedded in metallic matrix |
| FR2417829A1 (en) * | 1978-02-21 | 1979-09-14 | Gattys Ing Buero F J | METHOD FOR THE DENITRATION OF HIGHLY RADIOACTIVE RESIDUAL SOLUTIONS |
| FR2424611A1 (en) * | 1978-04-29 | 1979-11-23 | Kernforschungsz Karlsruhe | PROCESS FOR THE SOLIDIFICATION FOR THE END STORAGE, FAVORABLE TO THE ENVIRONMENT, OF AQUEOUS RADIO-ACTIVE LIQUID WASTE OF MEDIUM (MAW) AND LOW (LAW) ACTIVITY CATEGORIES, AND OF LIQUIDS CONTAINING TRITIUM COMPOUNDS |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2257737A1 (en) * | 1972-11-24 | 1974-05-30 | Kernforschung Gmbh Ges Fuer | Conditioning radioactive waste in glass blocks - by immersing in effluent sludge for sufficient time to reduce thermal power to a tenth |
| DE2609299C2 (en) * | 1976-03-06 | 1983-12-22 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Device for solidifying aqueous, radioactive waste solutions in a glass or ceramic-like block |
| US4072501A (en) * | 1977-04-13 | 1978-02-07 | The United States Of America As Represented By The United States Department Of Energy | Method of producing homogeneous mixed metal oxides and metal-metal oxide mixtures |
| DE2807324A1 (en) * | 1978-02-21 | 1979-08-23 | Franz Josef Gattys Ingenieurbu | Denitration of highly radioactive waste solns. - partic. using para-formaldehyde powder, producing reduced amt. of secondary radioactive waste |
| DE2900478A1 (en) * | 1979-01-08 | 1980-07-10 | Franz Josef Gattys Ingenieurbu | Denitration of highly radioactive waste solns. - partic. using para-formaldehyde powder, producing reduced amt. of secondary radioactive waste |
| DE2856466C2 (en) * | 1978-12-28 | 1986-01-23 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Process for solidifying highly radioactive waste materials in a metal matrix in the form of granules or powder |
| JPS5595900A (en) * | 1979-01-12 | 1980-07-21 | Hitachi Ltd | Radioactive waste processing method |
-
1982
- 1982-07-06 DE DE19823225199 patent/DE3225199A1/en not_active Ceased
-
1983
- 1983-07-04 WO PCT/EP1983/000168 patent/WO1984000440A1/en not_active Ceased
- 1983-07-04 EP EP83902092A patent/EP0112875A1/en not_active Withdrawn
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2835555A (en) * | 1953-11-17 | 1958-05-20 | Healy Thomas Victor | Reduction of acidity of nitric acid solutions by use of formaldehyde |
| US3603788A (en) * | 1968-05-06 | 1971-09-07 | Floro D Miraldi | Gamma radiation source and method for the treatment of sewage |
| FR2051704A1 (en) * | 1969-07-11 | 1971-04-09 | Kernforschung Gmbh Ges Fuer | |
| DE2524169A1 (en) * | 1975-05-31 | 1976-12-23 | Europaeische Ges Fuer Die Chem | High activity radioactive waste stabilised as solid - of active glass granulate embedded in metallic matrix |
| FR2417829A1 (en) * | 1978-02-21 | 1979-09-14 | Gattys Ing Buero F J | METHOD FOR THE DENITRATION OF HIGHLY RADIOACTIVE RESIDUAL SOLUTIONS |
| FR2424611A1 (en) * | 1978-04-29 | 1979-11-23 | Kernforschungsz Karlsruhe | PROCESS FOR THE SOLIDIFICATION FOR THE END STORAGE, FAVORABLE TO THE ENVIRONMENT, OF AQUEOUS RADIO-ACTIVE LIQUID WASTE OF MEDIUM (MAW) AND LOW (LAW) ACTIVITY CATEGORIES, AND OF LIQUIDS CONTAINING TRITIUM COMPOUNDS |
Also Published As
| Publication number | Publication date |
|---|---|
| DE3225199A1 (en) | 1984-01-12 |
| EP0112875A1 (en) | 1984-07-11 |
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