BE685007A - - Google Patents
Info
- Publication number
- BE685007A BE685007A BE685007DA BE685007A BE 685007 A BE685007 A BE 685007A BE 685007D A BE685007D A BE 685007DA BE 685007 A BE685007 A BE 685007A
- Authority
- BE
- Belgium
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
-
- 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
- C22B60/0204—Obtaining thorium, uranium, or other actinides obtaining uranium
- C22B60/0213—Obtaining thorium, uranium, or other actinides obtaining uranium by dry processes
-
- 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
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Mechanical Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Geology (AREA)
- Materials Engineering (AREA)
- Environmental & Geological Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacture And Refinement Of Metals (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US52632866 US3282681A (en) | 1966-02-08 | 1966-02-08 | Separation of uranium and plutonium values |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| BE685007A true BE685007A (ru) | 1967-01-16 |
Family
ID=24096886
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| BE685007D BE685007A (ru) | 1966-02-08 | 1966-08-03 |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US3282681A (ru) |
| BE (1) | BE685007A (ru) |
| DE (1) | DE1533138C3 (ru) |
| GB (1) | GB1137625A (ru) |
| SE (1) | SE307201B (ru) |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3326673A (en) * | 1966-09-23 | 1967-06-20 | James B Knighton | Process for separating plutonium from uranium from fission products |
| US3607145A (en) * | 1969-01-06 | 1971-09-21 | Atomic Energy Commission | Plutonium separation from uranium |
| US4234383A (en) * | 1969-05-19 | 1980-11-18 | Parlee-Anderson Corporation | Actinide nitride-fueled reactor and continuous method of operating the same |
| US4814046A (en) * | 1988-07-12 | 1989-03-21 | The United States Of America As Represented By The United States Department Of Energy | Process to separate transuranic elements from nuclear waste |
| US5096545A (en) * | 1991-05-21 | 1992-03-17 | The United States Of America As Represented By The United States Department Of Energy | Plutonium recovery from spent reactor fuel by uranium displacement |
| GB9111666D0 (en) * | 1991-05-31 | 1991-07-24 | British Nuclear Fuels Plc | A method of producing uranium metal |
| US5147616A (en) * | 1991-10-03 | 1992-09-15 | The United States Of America As Represented By The United States Department Of Energy | Magnesium transport extraction of transuranium elements from LWR fuel |
| US5160367A (en) * | 1991-10-03 | 1992-11-03 | The United States Of America As Represented By The United States Department Of Energy | Salt transport extraction of transuranium elements from lwr fuel |
| US5141723A (en) * | 1991-10-03 | 1992-08-25 | The United States Of America As Represented By The United States Department Of Energy | Uranium chloride extraction of transuranium elements from LWR fuel |
| US5202100A (en) * | 1991-11-07 | 1993-04-13 | Molten Metal Technology, Inc. | Method for reducing volume of a radioactive composition |
| US5732365A (en) * | 1995-10-30 | 1998-03-24 | Dakota Catalyst Products, Inc. | Method of treating mixed waste in a molten bath |
| RU2522905C1 (ru) * | 2012-11-26 | 2014-07-20 | Федеральное государственное автономное образовательное учреждение высшего профессионального образования "Уральский федеральный университет имени первого Президента России Б.Н. Ельцина" | Способ извлечения редкоземельных элементов из жидких сплавов с цинком |
Family Cites Families (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US2875021A (en) * | 1943-08-24 | 1959-02-24 | Harrison S Brown | Method of separating uranium values, plutonium values and fission products by chlorination |
| US2851333A (en) * | 1945-03-09 | 1958-09-09 | Harrison S Brown | Process of separating plutonium from uranium |
| US2917382A (en) * | 1957-08-14 | 1959-12-15 | Harold M Feder | Separation of plutonium from uranium |
| US2934425A (en) * | 1958-06-30 | 1960-04-26 | James B Knighton | Method for purifying uranium |
| US2948586A (en) * | 1958-07-24 | 1960-08-09 | Raymond H Moore | Fused salt process for recovery of values from used nuclear reactor fuels |
| US2968547A (en) * | 1959-12-18 | 1961-01-17 | Ward L Lyon | Production of plutonium metal |
| US3011865A (en) * | 1960-08-22 | 1961-12-05 | Glen E Benedict | Separation of uranium and plutonium oxides |
| BE620083A (ru) * | 1961-07-14 | 1900-01-01 | ||
| US3148975A (en) * | 1961-12-11 | 1964-09-15 | Dow Chemical Co | Processing impure uranium |
| US3148977A (en) * | 1961-12-11 | 1964-09-15 | Dow Chemical Co | Method of purifying uranium metal |
| US3120435A (en) * | 1962-06-04 | 1964-02-04 | Chiotti Premo | Regeneration of fission-products-containing magnesium-thorium alloys |
| US3169057A (en) * | 1962-10-29 | 1965-02-09 | James B Knighton | Separation of plutonium, uranium and fission products from each other |
| US3147109A (en) * | 1963-05-03 | 1964-09-01 | James B Knighton | Separation of plutonium, uranium, americium and fission products from each other |
| US3218160A (en) * | 1964-11-10 | 1965-11-16 | James B Knighton | Regeneration of nuclear fuel |
-
1966
- 1966-02-08 US US52632866 patent/US3282681A/en not_active Expired - Lifetime
- 1966-06-21 GB GB2766766A patent/GB1137625A/en not_active Expired
- 1966-08-03 BE BE685007D patent/BE685007A/xx unknown
- 1966-09-30 SE SE1320266A patent/SE307201B/xx unknown
- 1966-11-16 DE DE1533138A patent/DE1533138C3/de not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| SE307201B (ru) | 1968-12-23 |
| DE1533138C3 (de) | 1973-09-27 |
| DE1533138A1 (de) | 1970-01-02 |
| US3282681A (en) | 1966-11-01 |
| DE1533138B2 (de) | 1973-03-01 |
| GB1137625A (en) | 1968-12-27 |