GB938925A - Method for obtaining plutonium metal and alloys of plutonium from plutonium trichloride - Google Patents
Method for obtaining plutonium metal and alloys of plutonium from plutonium trichlorideInfo
- Publication number
- GB938925A GB938925A GB4142/61A GB414261A GB938925A GB 938925 A GB938925 A GB 938925A GB 4142/61 A GB4142/61 A GB 4142/61A GB 414261 A GB414261 A GB 414261A GB 938925 A GB938925 A GB 938925A
- Authority
- GB
- United Kingdom
- Prior art keywords
- plutonium
- cerium
- alloys
- trichloride
- alloy
- 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
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)
- Manufacture And Refinement Of Metals (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
938,925. Plutonium and plutonium alloys; nuclear fuel. UNITED STATES ATOMIC ENERGY COMMISSION. Feb. 3, 1961 [April 8, 1960], No. 4142/61. Drawings to Specification. Class 39 (4). Plutonium or plutonium alloys are obtained and plutonium is simultaneously decontaminated by reacting under an inert gas blanket a salt phase ; containing plutonium trichloride with cerium or cerium-cobalt alloy. The salt phase may consist of a eutectic mixture of plutonium trichloride and sodium chloride and may also contain LaCl 3 and CeCl 3 ; it may result from a process in which partially spent plutonium fuel displaces zinc in a chloride melt. The salt may be melted under argon in a MgOTiO 2 crucible and the reducing metal added as lumps of cerium-cobalt alloy or by lowering a rod of cerium into the melt. Reduction takes place at a temperature in the range 550-775‹ C. under about atmospheric pressure. Reduction with cerium yields a Pu-Ce alloy and with Ce-Co, a Pu-Ce-Co alloy ; these alloys are useful as reactor fuels. Apparatus is described with reference to drawings for carrying out the process in a batchwise fashion, semi-continuously, or continuously. Specifications 846,433 and 874,854 are referred to.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US21073A US3063829A (en) | 1960-04-08 | 1960-04-08 | Method for obtaining plutonium metal and alloys of plutonium from plutonium trichloride |
Publications (1)
Publication Number | Publication Date |
---|---|
GB938925A true GB938925A (en) | 1963-10-09 |
Family
ID=21802187
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB4142/61A Expired GB938925A (en) | 1960-04-08 | 1961-02-03 | Method for obtaining plutonium metal and alloys of plutonium from plutonium trichloride |
Country Status (3)
Country | Link |
---|---|
US (1) | US3063829A (en) |
BE (1) | BE602313A (en) |
GB (1) | GB938925A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2133205A (en) * | 1982-12-07 | 1984-07-18 | Westinghouse Electric Corp | Method of reversibly immobilizing sulfate ash |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4636250A (en) * | 1985-03-15 | 1987-01-13 | Elliott Guy R B | Recovery of uranium alloy |
US5104095A (en) * | 1990-03-12 | 1992-04-14 | Elliott Guy R B | Apparatus for separating molten salt from molten salt or molten uranium or molten uranium alloy |
US5118343A (en) * | 1991-04-23 | 1992-06-02 | The United States Of America As Represented By The United States Department Of Energy | Lithium metal reduction of plutonium oxide to produce plutonium metal |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2948586A (en) * | 1958-07-24 | 1960-08-09 | Raymond H Moore | Fused salt process for recovery of values from used nuclear reactor fuels |
-
1960
- 1960-04-08 US US21073A patent/US3063829A/en not_active Expired - Lifetime
-
1961
- 1961-02-03 GB GB4142/61A patent/GB938925A/en not_active Expired
- 1961-04-07 BE BE602313A patent/BE602313A/en unknown
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB2133205A (en) * | 1982-12-07 | 1984-07-18 | Westinghouse Electric Corp | Method of reversibly immobilizing sulfate ash |
Also Published As
Publication number | Publication date |
---|---|
US3063829A (en) | 1962-11-13 |
BE602313A (en) | 1961-07-31 |
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