CS167749B1 - Method of uranium,plutonium and their compounds gaining - Google Patents
Method of uranium,plutonium and their compounds gainingInfo
- Publication number
- CS167749B1 CS167749B1 CS213474A CS213474A CS167749B1 CS 167749 B1 CS167749 B1 CS 167749B1 CS 213474 A CS213474 A CS 213474A CS 213474 A CS213474 A CS 213474A CS 167749 B1 CS167749 B1 CS 167749B1
- Authority
- CS
- Czechoslovakia
- Prior art keywords
- plutonium
- uranium
- gaining
- compounds
- compounds gaining
- Prior art date
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
- C22B60/0204—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
- G21C19/34—Apparatus or processes for dismantling nuclear fuel, e.g. before reprocessing ; Apparatus or processes for dismantling strings of spent fuel elements
- G21C19/38—Chemical means only
-
- 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
-
- 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)
- Physics & Mathematics (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Organic Chemistry (AREA)
- General Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- Environmental & Geological Engineering (AREA)
- Geology (AREA)
- Metallurgy (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
Priority Applications (7)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CS213474A CS167749B1 (en) | 1974-03-25 | 1974-03-25 | Method of uranium,plutonium and their compounds gaining |
FR7508517A FR2273074B1 (fr) | 1974-03-25 | 1975-03-19 | |
SU752116307A SU631454A1 (ru) | 1974-03-25 | 1975-03-21 | Способ разрушени твэлов |
DE19752512552 DE2512552A1 (de) | 1974-03-25 | 1975-03-21 | Verfahren zur abtrennung von uran, plutonium und deren verbindungen |
JP3456975A JPS50140794A (fr) | 1974-03-25 | 1975-03-24 | |
US05/561,191 US4024068A (en) | 1974-03-24 | 1975-03-24 | Process for separating ceramics of uranium and plutonium from zirconium by hydriding and mixtures thereof |
CS542678A CS197150B3 (cs) | 1974-03-25 | 1978-08-18 | Způsob oddělování kovových povlakových a konstrukčních materiálů palivových článků jaderných reaktorů, vytvořených ze zirkonia nebo jeho slitin, od jaderného paliva |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CS213474A CS167749B1 (en) | 1974-03-25 | 1974-03-25 | Method of uranium,plutonium and their compounds gaining |
Publications (1)
Publication Number | Publication Date |
---|---|
CS167749B1 true CS167749B1 (en) | 1976-05-28 |
Family
ID=5357575
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CS213474A CS167749B1 (en) | 1974-03-24 | 1974-03-25 | Method of uranium,plutonium and their compounds gaining |
Country Status (6)
Country | Link |
---|---|
US (1) | US4024068A (fr) |
JP (1) | JPS50140794A (fr) |
CS (1) | CS167749B1 (fr) |
DE (1) | DE2512552A1 (fr) |
FR (1) | FR2273074B1 (fr) |
SU (1) | SU631454A1 (fr) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4296074A (en) * | 1978-04-10 | 1981-10-20 | Rockwell International Corporation | Method of decladding |
DE3011760A1 (de) * | 1980-03-26 | 1981-10-01 | Kraftwerk Union AG, 4330 Mülheim | Verfahren zum zerlegen abgebrannter kernreaktorbrennstaebe |
JP2633000B2 (ja) * | 1989-01-28 | 1997-07-23 | 動力炉・核燃料開発事業団 | 高放射性廃棄物の処理方法 |
AU2792100A (en) † | 1999-04-07 | 2000-11-14 | Trub Ag | Data carrier and method for producing same |
JP2013101066A (ja) * | 2011-11-09 | 2013-05-23 | Hitachi-Ge Nuclear Energy Ltd | ジルコニウムを含む使用済燃料の処理装置および方法 |
Family Cites Families (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2827405A (en) * | 1956-05-09 | 1958-03-18 | Ca Atomic Energy Ltd | Method of desheathing of uranium fuel rods |
US3776508A (en) * | 1961-05-26 | 1973-12-04 | Atomic Energy Commission | Process for massively hydriding zirconium-uranium fuel elements |
US3343924A (en) * | 1966-09-30 | 1967-09-26 | Louis J Anastasia | Selective decladding of nuclear fuel elements |
US3720752A (en) * | 1967-04-11 | 1973-03-13 | Houten R Van | Massive metal hydride structures and methods for their preparation |
US3644104A (en) * | 1968-10-23 | 1972-02-22 | Georges Manevy | Process for processing canned irradiated ceramic fuel elements |
US3659107A (en) * | 1970-07-29 | 1972-04-25 | Atomic Energy Commission | Radioisotopic fuel capsule |
US3715204A (en) * | 1971-05-28 | 1973-02-06 | Atomic Energy Commission | Separation of plutonium and uranium from holder |
-
1974
- 1974-03-25 CS CS213474A patent/CS167749B1/cs unknown
-
1975
- 1975-03-19 FR FR7508517A patent/FR2273074B1/fr not_active Expired
- 1975-03-21 DE DE19752512552 patent/DE2512552A1/de not_active Withdrawn
- 1975-03-21 SU SU752116307A patent/SU631454A1/ru active
- 1975-03-24 JP JP3456975A patent/JPS50140794A/ja active Pending
- 1975-03-24 US US05/561,191 patent/US4024068A/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
SU631454A1 (ru) | 1978-11-05 |
FR2273074B1 (fr) | 1980-04-04 |
JPS50140794A (fr) | 1975-11-12 |
DE2512552A1 (de) | 1975-11-27 |
US4024068A (en) | 1977-05-17 |
FR2273074A1 (fr) | 1975-12-26 |
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