WO1984000440A1 - Procede de traitement d'elements de combustibles apres leur extraction du coeur d'un reacteur - Google Patents
Procede de traitement d'elements de combustibles apres leur extraction du coeur d'un reacteur 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
Les éléments sont dissous à chaud dans de l'acide nitrique et la solution qui est débarassée des impuretés solides ainsi que de l'uranium et du plutonium réutilisables est d'abord soumise à une concentration et une dénitration. La dénitration se fait en plusieurs étapes pour provoquer la séparation sélective des constituants de la solution. Les déchets oxydés sont transformés en granulés. La dénitration dans une première étape se fait avec de l'acide formique et dans une seconde étape avec du paraformaldéhyde ou de l'acide oxalique. S'il s'agit de matériel qui se transforme difficilement en pellets (granulés), cette transformation a lieu avec une substance minérale qui réagit avec l'eau pour former une substance insoluble dans l'eau (en particulier un hydroxyde d'un métal du groupe principal ou secondaire II du tableau périodique des éléments). Cette transformation a lieu dans une couche mince sur les granulés produits. Les pellets (granulés) peuvent être utilisés sous cette forme ou fondus pour former des corps de verre ou de céramique.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE19823225199 DE3225199A1 (de) | 1982-07-06 | 1982-07-06 | Verfahren zur aufbereitung von abgebrannten brennelementen aus kernreaktoren |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| WO1984000440A1 true WO1984000440A1 (fr) | 1984-02-02 |
Family
ID=6167731
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| PCT/EP1983/000168 Ceased WO1984000440A1 (fr) | 1982-07-06 | 1983-07-04 | Procede de traitement d'elements de combustibles apres leur extraction du coeur d'un reacteur |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP0112875A1 (fr) |
| DE (1) | DE3225199A1 (fr) |
| WO (1) | WO1984000440A1 (fr) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2779974B1 (fr) | 1998-06-19 | 2000-07-13 | Commissariat Energie Atomique | Procede de dissolution du plutonium ou d'un alliage de plutonium |
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 (fr) * | 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 (de) * | 1975-05-31 | 1976-12-23 | Europaeische Ges Fuer Die Chem | Hochradioaktiven abfall enthaltende koerper und verfahren zu ihrer herstellung |
| FR2417829A1 (fr) * | 1978-02-21 | 1979-09-14 | Gattys Ing Buero F J | Procede pour la denitration de solutions residuaires fortement radioactives |
| FR2424611A1 (fr) * | 1978-04-29 | 1979-11-23 | Kernforschungsz Karlsruhe | Procede pour la solidification destinee au stockage final, favorable a l'environnement, de dechets liquides radio-actifs aqueux des categories d'activite moyenne (maw) et faible (law), et de liquides contenant des composes du tritium |
Family Cites Families (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2257737A1 (de) * | 1972-11-24 | 1974-05-30 | Kernforschung Gmbh Ges Fuer | Verfahren zum konditionieren von hochradioaktiven, verfestigten abfaellen |
| DE2609299C2 (de) * | 1976-03-06 | 1983-12-22 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Vorrichtung zur Verfestigung von wäßrigen, radioaktiven Abfall-Lösungen in einem glas- oder keramikartigen 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 (de) * | 1978-02-21 | 1979-08-23 | Franz Josef Gattys Ingenieurbu | Verfahren zur denitration von hochradioaktiven abfall-loesungen |
| DE2900478A1 (de) * | 1979-01-08 | 1980-07-10 | Franz Josef Gattys Ingenieurbu | Verfahren zur denitration von radioaktiven abfalloesungen |
| DE2856466C2 (de) * | 1978-12-28 | 1986-01-23 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Verfahren zur Verfestigung hochradioaktive Abfallstoffe enthaltender, als Granalien oder als Pulver vorliegender Glasteilchen in einer Metallmatrix |
| JPS5595900A (en) * | 1979-01-12 | 1980-07-21 | Hitachi Ltd | Radioactive waste processing method |
-
1982
- 1982-07-06 DE DE19823225199 patent/DE3225199A1/de not_active Ceased
-
1983
- 1983-07-04 WO PCT/EP1983/000168 patent/WO1984000440A1/fr not_active Ceased
- 1983-07-04 EP EP83902092A patent/EP0112875A1/fr 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 (fr) * | 1969-07-11 | 1971-04-09 | Kernforschung Gmbh Ges Fuer | |
| DE2524169A1 (de) * | 1975-05-31 | 1976-12-23 | Europaeische Ges Fuer Die Chem | Hochradioaktiven abfall enthaltende koerper und verfahren zu ihrer herstellung |
| FR2417829A1 (fr) * | 1978-02-21 | 1979-09-14 | Gattys Ing Buero F J | Procede pour la denitration de solutions residuaires fortement radioactives |
| FR2424611A1 (fr) * | 1978-04-29 | 1979-11-23 | Kernforschungsz Karlsruhe | Procede pour la solidification destinee au stockage final, favorable a l'environnement, de dechets liquides radio-actifs aqueux des categories d'activite moyenne (maw) et faible (law), et de liquides contenant des composes du tritium |
Also Published As
| Publication number | Publication date |
|---|---|
| DE3225199A1 (de) | 1984-01-12 |
| EP0112875A1 (fr) | 1984-07-11 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| AK | Designated states |
Designated state(s): SU US |
|
| AL | Designated countries for regional patents |
Designated state(s): BE FR GB |
|
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