CH419060A - Procedimento per il ricupero di uranio arricchito in isotopo 233 o 235 da combustibili a base di leghe di uranio-alluminio impiegati nei reattori nucleari - Google Patents
Procedimento per il ricupero di uranio arricchito in isotopo 233 o 235 da combustibili a base di leghe di uranio-alluminio impiegati nei reattori nucleariInfo
- Publication number
- CH419060A CH419060A CH1254562A CH1254562A CH419060A CH 419060 A CH419060 A CH 419060A CH 1254562 A CH1254562 A CH 1254562A CH 1254562 A CH1254562 A CH 1254562A CH 419060 A CH419060 A CH 419060A
- Authority
- CH
- Switzerland
- Prior art keywords
- uranium
- isotope
- recovery
- aluminum alloys
- nuclear reactors
- Prior art date
Links
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
- G21C19/46—Aqueous processes, e.g. by using organic extraction means, including the regeneration of these means
-
- 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
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0221—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching
- C22B60/0226—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors
- C22B60/0239—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agent
-
- 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
- C22B60/0217—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
- C22B60/0252—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
- C22B60/026—Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solvents
-
- 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)
- General Life Sciences & Earth Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Chemical & Material 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)
- Inorganic Compounds Of Heavy Metals (AREA)
- Extraction Or Liquid Replacement (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
IT189562 | 1962-02-02 |
Publications (1)
Publication Number | Publication Date |
---|---|
CH419060A true CH419060A (it) | 1966-08-31 |
Family
ID=11102085
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CH1254562A CH419060A (it) | 1962-02-02 | 1962-10-25 | Procedimento per il ricupero di uranio arricchito in isotopo 233 o 235 da combustibili a base di leghe di uranio-alluminio impiegati nei reattori nucleari |
Country Status (4)
Country | Link |
---|---|
BE (1) | BE620945A (it) |
CH (1) | CH419060A (it) |
DK (1) | DK108762C (it) |
GB (1) | GB1024751A (it) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US9896738B2 (en) * | 2015-05-28 | 2018-02-20 | Savannah River Nuclear Solutions, Llc | Process for dissolving aluminum for recovering nuclear fuel |
CN110373556A (zh) * | 2019-07-05 | 2019-10-25 | 湖南稀土金属材料研究院 | 从锆工业废渣中回收放射性元素的方法 |
-
0
- BE BE620945D patent/BE620945A/xx unknown
-
1962
- 1962-10-25 CH CH1254562A patent/CH419060A/it unknown
- 1962-11-20 GB GB4383562A patent/GB1024751A/en not_active Expired
- 1962-12-04 DK DK524162A patent/DK108762C/da active
Also Published As
Publication number | Publication date |
---|---|
DK108762C (da) | 1968-02-05 |
GB1024751A (en) | 1966-04-06 |
BE620945A (it) | 1900-01-01 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
BE605763A (fr) | Procédé pour la récupération du plutonium à partir du combustible d'uranium bombardé par des neutrons | |
IT944898B (it) | Processo per separare isotopi di uranio | |
IT1052550B (it) | Procedimento per l arricchimento isotopico di uranio e boro | |
IT1013390B (it) | Perfezionamento nei reattori nuclea ri | |
FR1229842A (fr) | Réacteur nucléaire à réfrigérant gazeux | |
CH419060A (it) | Procedimento per il ricupero di uranio arricchito in isotopo 233 o 235 da combustibili a base di leghe di uranio-alluminio impiegati nei reattori nucleari | |
FR1335072A (fr) | Procédé de séparation de l'uranium, du plutonium et des produits de fission provenant d'uranium bombardé par des neutrons | |
FR1387127A (fr) | Procédé de séparation de l'uranium et du plutonium | |
CH391908A (fr) | Réacteur nucléaire à modérateur liquide | |
GB996239A (en) | Improvements in or relating to nuclear fusion reactors | |
CH385361A (fr) | Aire de support du modérateur solide d'un réacteur nucléaire | |
CH477361A (de) | Verfahren zum Komprimieren der schwereren Isotope des Wasserstoffes, Deuterium und Tritium | |
FR1332984A (fr) | Alliages d'uranium et combustibles nucléaires contenant lesdits alliages | |
FR1329999A (fr) | Perfectionnements aux combustibles nucléaires à base d'uranium enrichis en plutonium | |
IT957696B (it) | Processo per separare uranio da plutonio | |
CH372389A (de) | Atomkernreaktor-Anlage | |
FR1334010A (fr) | Procédé pour la récupération de l'uranium, enrichi en isotope 233 ou 235, dans les combustibles à base d'alliages d'uranium et d'aluminium utilisés dans les réacteurs nucléaires | |
GB999699A (en) | Improvements in or relating to nuclear reactors | |
FR1337006A (fr) | Procédé pour la séparation du plutonium pur, de l'uranium pur et du thorium pur de leurs impuretés | |
FR1206682A (fr) | Procédé d'enrichisement d'isotopes | |
CA640102A (en) | Process for the separation of elements 93 (neptunium) and 94 (plutonium) from irradiated uranium salts | |
DK103420C (da) | Legering til anvendelse i atomkernereaktorer. | |
FR1254109A (fr) | Alliage à base d'uranium, pouvant être utilisé dans un réacteur nucléaire | |
FR1245297A (fr) | Procédé de production d'uranium et de plutonium métalliques à partir de leurs halogénures | |
IT952166B (it) | Barra di assorbimento per reattori nucleari |