GB2105096A - Process for the reprocessing of irradiated nuclear fuels - Google Patents
Process for the reprocessing of irradiated nuclear fuels Download PDFInfo
- Publication number
- GB2105096A GB2105096A GB08216895A GB8216895A GB2105096A GB 2105096 A GB2105096 A GB 2105096A GB 08216895 A GB08216895 A GB 08216895A GB 8216895 A GB8216895 A GB 8216895A GB 2105096 A GB2105096 A GB 2105096A
- Authority
- GB
- United Kingdom
- Prior art keywords
- residue
- reprocessing
- plutonium
- fuels
- irradiated nuclear
- 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.)
- Granted
Links
- 238000012958 reprocessing Methods 0.000 title claims abstract description 12
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 8
- 238000000034 method Methods 0.000 title claims description 21
- 230000001590 oxidative effect Effects 0.000 claims abstract description 7
- 239000002253 acid Substances 0.000 claims abstract description 5
- 229910001854 alkali hydroxide Inorganic materials 0.000 claims abstract description 5
- 150000008044 alkali metal hydroxides Chemical class 0.000 claims abstract description 5
- 238000001035 drying Methods 0.000 claims abstract description 3
- 230000002285 radioactive effect Effects 0.000 claims abstract description 3
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 claims description 18
- 229910052778 Plutonium Inorganic materials 0.000 claims description 14
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 12
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 8
- 229910017604 nitric acid Inorganic materials 0.000 claims description 8
- 239000000446 fuel Substances 0.000 claims description 6
- 238000004519 manufacturing process Methods 0.000 claims description 6
- FLDALJIYKQCYHH-UHFFFAOYSA-N plutonium(IV) oxide Inorganic materials [O-2].[O-2].[Pu+4] FLDALJIYKQCYHH-UHFFFAOYSA-N 0.000 claims description 6
- VWDWKYIASSYTQR-UHFFFAOYSA-N sodium nitrate Inorganic materials [Na+].[O-][N+]([O-])=O VWDWKYIASSYTQR-UHFFFAOYSA-N 0.000 claims description 6
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 claims description 4
- GABXYUQCUHMHDP-UHFFFAOYSA-N americium dioxide Inorganic materials [O-2].[O-2].[Am+4] GABXYUQCUHMHDP-UHFFFAOYSA-N 0.000 claims description 4
- 238000006243 chemical reaction Methods 0.000 claims description 4
- 239000000047 product Substances 0.000 claims description 4
- 229910052695 Americium Inorganic materials 0.000 claims description 2
- BQCADISMDOOEFD-UHFFFAOYSA-N Silver Chemical compound [Ag] BQCADISMDOOEFD-UHFFFAOYSA-N 0.000 claims description 2
- HPWBMQLLXMZFDK-UHFFFAOYSA-N [O--].[O--].[O--].[Am+3].[Am+3] Chemical class [O--].[O--].[O--].[Am+3].[Am+3] HPWBMQLLXMZFDK-UHFFFAOYSA-N 0.000 claims description 2
- 150000007513 acids Chemical class 0.000 claims description 2
- 150000001407 americium compounds Chemical class 0.000 claims description 2
- 239000007795 chemical reaction product Substances 0.000 claims description 2
- 238000000354 decomposition reaction Methods 0.000 claims description 2
- 238000001514 detection method Methods 0.000 claims description 2
- 238000002474 experimental method Methods 0.000 claims description 2
- 239000012527 feed solution Substances 0.000 claims description 2
- 230000004992 fission Effects 0.000 claims description 2
- 238000011084 recovery Methods 0.000 claims description 2
- 229910052709 silver Inorganic materials 0.000 claims description 2
- 239000004332 silver Substances 0.000 claims description 2
- 235000010344 sodium nitrate Nutrition 0.000 claims description 2
- 230000001988 toxicity Effects 0.000 claims description 2
- 231100000419 toxicity Toxicity 0.000 claims description 2
- 239000002699 waste material Substances 0.000 claims description 2
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
- G21C19/48—Non-aqueous processes
-
- 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)
- Inorganic Compounds Of Heavy Metals (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
In the reprocessing of irradiated nuclear fuels, wherein a radioactive residue occurs which is insoluble in acid, this residue, after drying, is rendered soluble by being treated at a relatively high temperature with a dry alkali hydroxide under oxidizing conditions.
Description
SPECIFICATION
Process for the reprocessing of irradiated nuclear fuels
The present invention relates to the reprocessing of irradiated nuclear fuels.
During the reprocessing of fuels containing plutonium, in accordance with the known PUREX process, insoluble residues are obtained which, interalia, contain plutonium. According to the production conditions of the fuel and the irradiation conditions, this residue can amount to as much as several percent of the plutonium used.
The residue is highly radioactive and very dangerous, and it is absolutely necessary for it to be brought into a soluble state and processed further.
The present invention lies in treating the dry residue, which is not soluble in nitric acid or other strong acids and which arises in the first stage of the
PUREX process, with dry alkali hydroxides under oxidizing conditions and at a high temperature.
Preferably, the dry residue is heated in a molar ratio of about 1:4 very intimately mixed with NaOH and is dried at 1 200C in dry air free of CO2, or in an equivalent oxidizing gas stream, for about 12 hours between 550 and 800 C.
Accordingly, interalia the Pu contained in the residue, which is insoluble in nitric acid, is converted into its ternary oxide having the empirical formula
NaePuOs. Under the reaction conditions, soluble ternary oxides of the fission products are also partly formed. The conversion to the corresponding americium compound is incomplete, since at these temperatures the high-valency ternary americium oxides are no longer stable.
A number of experiments were carried out in accordance with the above-described process. At least 99% of the 270 mg of PuO2 present in a residue of 1100 mg were dissolved. (Since undissolved
AmO2 was still present, 3 mg was the detection limit for Pu.) In the case of an assumed residue of PuO2 of 2%, a decomposition of 99% of the residue signifies that 99.98% of the plutonium can be fed to the recovery process.
It should be mentioned that the reaction product could be dissolved in 3 to 6 molar HNO3 (according to the requirements of the PUREX-Feed-solution).
The additional feed of NaN03 into the process will lie within the order of magnitude of the NaNO3 present.
As already mentioned, in the process according to the invention the plutonium losses are reduced during reprocessing. Not only the economy of the Pu cycle is improved, but also the toxicity of the waste is reduced. It is possible to avoid the expensive production processes which lead to a multiplication of the production cost of plutonium-containing fuels.
Example
1100 mg of residue with 270 mg of PuO2 and 7 mg of AmO2 were heated with NaOH for 12 hours at 600"C in a silver vessel, in accordance with the invention. The resultant product was dissolved in nitric acid and filtered. In the filter residue Pu and Am were no longer measurable.
1. A process for the reprocessing of irradiated nuclear fuels, wherein a residue occurs which is insoluble in acid, characterised in that the residue, after drying, is treated at a relatively high temperature with an alkali hydroxide under oxidizing conditions.
2. A process as claimed in claim 1, wherein the residue is heated for about 12 hours at from 550 to 800"C with NaOH.
3. A process as claimed in claim 1 substantially as hereinbefore described.
4. A process as claimed in claim 1 substantially as hereinbefore described in the specific Example.
**WARNING** end of DESC field may overlap start of CLMS **.
Claims (4)
1. A process for the reprocessing of irradiated nuclear fuels, wherein a residue occurs which is insoluble in acid, characterised in that the residue, after drying, is treated at a relatively high temperature with an alkali hydroxide under oxidizing conditions.
2. A process as claimed in claim 1, wherein the residue is heated for about 12 hours at from 550 to 800"C with NaOH.
3. A process as claimed in claim 1 substantially as hereinbefore described.
4. A process as claimed in claim 1 substantially as hereinbefore described in the specific Example.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| LU83452A LU83452A1 (en) | 1981-06-24 | 1981-06-24 | METHOD FOR REPROCESSING IRRADIATED NUCLEAR FUELS |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB2105096A true GB2105096A (en) | 1983-03-16 |
| GB2105096B GB2105096B (en) | 1985-10-09 |
Family
ID=19729677
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB8216895A Expired GB2105096B (en) | 1981-06-24 | 1982-06-10 | Process for the reprocessing of irradiated nuclear fuels |
Country Status (6)
| Country | Link |
|---|---|
| BE (1) | BE893514A (en) |
| DE (1) | DE3221688A1 (en) |
| FR (1) | FR2508692B1 (en) |
| GB (1) | GB2105096B (en) |
| IT (1) | IT1148342B (en) |
| LU (1) | LU83452A1 (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE102010036737A1 (en) * | 2010-07-29 | 2012-02-02 | Erwin Krüger | Process for the dry reprocessing of spent nuclear fuel (irradiated) and an apparatus for carrying out the process |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1199748B (en) * | 1963-05-15 | 1965-09-02 | Kernforschung Mit Beschraenkte | Process for processing irradiated nuclear fuel |
| DE1467322B2 (en) * | 1964-06-10 | 1972-06-22 | Europäische Atomgemeinschaft (EURATOM), Brüssel | PROCESS FOR THE RECYCLING OF OXYDIC NUCLEAR REACTOR FUEL |
| FR1483117A (en) * | 1965-06-10 | 1967-06-02 | Kernforschungsanlage Juelich | Process for the preparation of coated nuclear fuels |
-
1981
- 1981-06-24 LU LU83452A patent/LU83452A1/en unknown
-
1982
- 1982-06-04 DE DE3221688A patent/DE3221688A1/en not_active Withdrawn
- 1982-06-10 GB GB8216895A patent/GB2105096B/en not_active Expired
- 1982-06-15 BE BE1/10530A patent/BE893514A/en not_active IP Right Cessation
- 1982-06-23 IT IT4869282A patent/IT1148342B/en active
- 1982-06-24 FR FR8211092A patent/FR2508692B1/en not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| GB2105096B (en) | 1985-10-09 |
| LU83452A1 (en) | 1981-10-29 |
| FR2508692A1 (en) | 1982-12-31 |
| IT8248692A0 (en) | 1982-06-23 |
| IT1148342B (en) | 1986-12-03 |
| FR2508692B1 (en) | 1988-08-05 |
| BE893514A (en) | 1982-10-01 |
| DE3221688A1 (en) | 1983-01-13 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PCNP | Patent ceased through non-payment of renewal fee |