FR2074812A1 - Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosion - Google Patents
Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosionInfo
- Publication number
- FR2074812A1 FR2074812A1 FR7003424A FR7003424A FR2074812A1 FR 2074812 A1 FR2074812 A1 FR 2074812A1 FR 7003424 A FR7003424 A FR 7003424A FR 7003424 A FR7003424 A FR 7003424A FR 2074812 A1 FR2074812 A1 FR 2074812A1
- Authority
- FR
- France
- Prior art keywords
- fluorine ions
- nuclear fuel
- ions during
- during evaporation
- fuel recovery
- 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.)
- Withdrawn
Links
- 229910052731 fluorine Inorganic materials 0.000 title abstract 3
- 239000011737 fluorine Substances 0.000 title abstract 3
- -1 fluorine ions Chemical class 0.000 title abstract 3
- 230000007797 corrosion Effects 0.000 title abstract 2
- 238000005260 corrosion Methods 0.000 title abstract 2
- 230000008020 evaporation Effects 0.000 title abstract 2
- 238000001704 evaporation Methods 0.000 title abstract 2
- 239000003758 nuclear fuel Substances 0.000 title 1
- 238000011084 recovery Methods 0.000 title 1
- 239000008346 aqueous phase Substances 0.000 abstract 2
- YCKRFDGAMUMZLT-UHFFFAOYSA-N Fluorine atom Chemical compound [F] YCKRFDGAMUMZLT-UHFFFAOYSA-N 0.000 abstract 1
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 abstract 1
- 229910052778 Plutonium Inorganic materials 0.000 abstract 1
- 229910052770 Uranium Inorganic materials 0.000 abstract 1
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 abstract 1
- 229910052782 aluminium Inorganic materials 0.000 abstract 1
- 239000004411 aluminium Substances 0.000 abstract 1
- 238000009833 condensation Methods 0.000 abstract 1
- 230000005494 condensation Effects 0.000 abstract 1
- 230000004992 fission Effects 0.000 abstract 1
- 229910017604 nitric acid Inorganic materials 0.000 abstract 1
- 239000012074 organic phase Substances 0.000 abstract 1
- 239000003960 organic solvent Substances 0.000 abstract 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 abstract 1
- 238000001556 precipitation Methods 0.000 abstract 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 abstract 1
- 229910000166 zirconium phosphate Inorganic materials 0.000 abstract 1
- LEHFSLREWWMLPU-UHFFFAOYSA-B zirconium(4+);tetraphosphate Chemical compound [Zr+4].[Zr+4].[Zr+4].[O-]P([O-])([O-])=O.[O-]P([O-])([O-])=O.[O-]P([O-])([O-])=O.[O-]P([O-])([O-])=O LEHFSLREWWMLPU-UHFFFAOYSA-B 0.000 abstract 1
Classifications
-
- 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
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Extraction Or Liquid Replacement (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
Nuclear fission products are treated with nitric acid solution and put in contact with an organic solvent to extract uranium and plutonium. Fluoride ions are added to avoid zirconium phosphate precipitation. The organic and aqueous phases are separated, and an evaporation and condensation system used to recover the aqueous phase contents. The problem of rapid corrosion of apparatus by fluorine is overcome by the addition of aluminium to fix the fluorine ions in solution.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7003424A FR2074812A1 (en) | 1970-01-30 | 1970-01-30 | Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosion |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR7003424A FR2074812A1 (en) | 1970-01-30 | 1970-01-30 | Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosion |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| FR2074812A1 true FR2074812A1 (en) | 1971-10-08 |
Family
ID=9049879
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| FR7003424A Withdrawn FR2074812A1 (en) | 1970-01-30 | 1970-01-30 | Nuclear fuel recovery - fixing fluorine ions during evaporation to avoid corrosion |
Country Status (1)
| Country | Link |
|---|---|
| FR (1) | FR2074812A1 (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2480019A1 (en) * | 1980-04-08 | 1981-10-09 | Etu En Nucleaire Centre | METHOD FOR EXTRACTING FLUORIDE IONS FROM A SOLUTION OF NUCLEAR FUELS |
| WO2001033575A3 (en) * | 1999-10-29 | 2001-11-29 | Ca Atomic Energy Ltd | Process for recycling irradiated fuel |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1299513A (en) * | 1960-03-07 | 1962-07-27 | Atomic Energy Commission | Process for dissolving uranium and zirconium compositions |
-
1970
- 1970-01-30 FR FR7003424A patent/FR2074812A1/en not_active Withdrawn
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1299513A (en) * | 1960-03-07 | 1962-07-27 | Atomic Energy Commission | Process for dissolving uranium and zirconium compositions |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2480019A1 (en) * | 1980-04-08 | 1981-10-09 | Etu En Nucleaire Centre | METHOD FOR EXTRACTING FLUORIDE IONS FROM A SOLUTION OF NUCLEAR FUELS |
| WO2001033575A3 (en) * | 1999-10-29 | 2001-11-29 | Ca Atomic Energy Ltd | Process for recycling irradiated fuel |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| ST | Notification of lapse |