GB1324024A - Method for the separation of neptunium and plutonium - Google Patents
Method for the separation of neptunium and plutoniumInfo
- Publication number
- GB1324024A GB1324024A GB4687470A GB4687470A GB1324024A GB 1324024 A GB1324024 A GB 1324024A GB 4687470 A GB4687470 A GB 4687470A GB 4687470 A GB4687470 A GB 4687470A GB 1324024 A GB1324024 A GB 1324024A
- Authority
- GB
- United Kingdom
- Prior art keywords
- solution
- separation
- organic solvent
- aqueous
- oct
- 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
Links
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/04—Obtaining plutonium
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
- C22B60/00—Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
- C22B60/02—Obtaining thorium, uranium, or other actinides
- C22B60/0295—Obtaining thorium, uranium, or other actinides obtaining other actinides except plutonium
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Geology (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Manufacturing & Machinery (AREA)
- Environmental & Geological Engineering (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Extraction Or Liquid Replacement (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
1324024 Separation of neptunium and plutonium COMMISSARIAT A L'ENERGIE ATOMIQUE 2 Oct 1970 [3 Oct 1969] 46874/70 Heading G6R An organic solvent solution containing Np and Pu is contacted with an aqueous sulphuric and nitric acid solution containing a reducing agent, e.g. ferrous sulphamate; the Pu forms a complex and passes into the aqueous phase, while the Np remains in the organic solvent. The organic solution may be obtained by extraction of an aqueous feed solution with a tertiary amine, e.g. trilauryl amine in dodecane; if the feed solution is reducing, Np is selectively extracted. The aqueous feed or sulphate-containing solution may include hydrazine to prevent oxidation of Fe II or Pu III. A phosphine oxide is referred to as an alternative organic solvent. The process may be used for the recovery of Np 237 in the reprocessing of spent nuclear fuel or for the separation of Pu 238 from irradiated Np 237.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR6933809A FR2111990B1 (en) | 1969-10-03 | 1969-10-03 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1324024A true GB1324024A (en) | 1973-07-18 |
Family
ID=9041003
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB4687470A Expired GB1324024A (en) | 1969-10-03 | 1970-10-02 | Method for the separation of neptunium and plutonium |
Country Status (3)
Country | Link |
---|---|
DE (1) | DE2048527C2 (en) |
FR (1) | FR2111990B1 (en) |
GB (1) | GB1324024A (en) |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE3843887C1 (en) * | 1988-12-24 | 1990-06-21 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe, De | |
FR3015760B1 (en) * | 2013-12-20 | 2016-01-29 | Commissariat Energie Atomique | PROCESS FOR TREATING A USE NUCLEAR FUEL COMPRISING A DECONTAMINATION STEP OF URANIUM (VI) IN AT LEAST ONE ACTINIDE (IV) BY COMPLEXATION OF THIS ACTINIDE (IV) |
CN106893878B (en) * | 2017-03-02 | 2018-11-30 | 中国原子能科学研究院 | A method of recycling plutonium from radioactivity spentnuclear fuel |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR1387127A (en) * | 1963-11-26 | 1965-01-29 | Commissariat Energie Atomique | Uranium and plutonium separation process |
-
1969
- 1969-10-03 FR FR6933809A patent/FR2111990B1/fr not_active Expired
-
1970
- 1970-10-02 GB GB4687470A patent/GB1324024A/en not_active Expired
- 1970-10-02 DE DE19702048527 patent/DE2048527C2/en not_active Expired
Also Published As
Publication number | Publication date |
---|---|
FR2111990B1 (en) | 1973-12-21 |
DE2048527A1 (en) | 1971-04-15 |
FR2111990A1 (en) | 1972-06-16 |
DE2048527C2 (en) | 1983-07-21 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
435 | Patent endorsed 'licences of right' on the date specified (sect. 35/1949) | ||
PCNP | Patent ceased through non-payment of renewal fee |