GB1142497A - A process for recovering uranium from zirconium clad uranium bearing nuclear fuel elements - Google Patents
A process for recovering uranium from zirconium clad uranium bearing nuclear fuel elementsInfo
- Publication number
- GB1142497A GB1142497A GB39516/66A GB3951666A GB1142497A GB 1142497 A GB1142497 A GB 1142497A GB 39516/66 A GB39516/66 A GB 39516/66A GB 3951666 A GB3951666 A GB 3951666A GB 1142497 A GB1142497 A GB 1142497A
- Authority
- GB
- United Kingdom
- Prior art keywords
- uranium
- nuclear fuel
- zirconium
- fuel elements
- recovering
- 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
- 229910052770 Uranium Inorganic materials 0.000 title abstract 5
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title abstract 5
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 title 1
- 229910052726 zirconium Inorganic materials 0.000 title 1
- RVTZCBVAJQQJTK-UHFFFAOYSA-N oxygen(2-);zirconium(4+) Chemical compound [O-2].[O-2].[Zr+4] RVTZCBVAJQQJTK-UHFFFAOYSA-N 0.000 abstract 2
- 229910001928 zirconium oxide Inorganic materials 0.000 abstract 2
- 229910018072 Al 2 O 3 Inorganic materials 0.000 abstract 1
- HUOJAJIXHLNXLN-UHFFFAOYSA-N fluoro hypofluorite zirconium Chemical compound [Zr].FOF HUOJAJIXHLNXLN-UHFFFAOYSA-N 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
- 239000002245 particle Substances 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- SANRKQGLYCLAFE-UHFFFAOYSA-H uranium hexafluoride Chemical compound F[U](F)(F)(F)(F)F SANRKQGLYCLAFE-UHFFFAOYSA-H 0.000 abstract 1
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
- G21C19/34—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
-
- 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
- C22B34/00—Obtaining refractory metals
- C22B34/10—Obtaining titanium, zirconium or hafnium
- C22B34/14—Obtaining zirconium or hafnium
-
- 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
-
- 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
-
- 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
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Mechanical Engineering (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Manufacturing & Machinery (AREA)
- Materials Engineering (AREA)
- Life Sciences & Earth Sciences (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Physics & Mathematics (AREA)
- Environmental & Geological Engineering (AREA)
- Geology (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US527383A US3294492A (en) | 1966-02-11 | 1966-02-11 | Process for decladding zirconium from zirconium clad nuclear fuel elements |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1142497A true GB1142497A (en) | 1969-02-05 |
Family
ID=24101248
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB39516/66A Expired GB1142497A (en) | 1966-02-11 | 1966-09-05 | A process for recovering uranium from zirconium clad uranium bearing nuclear fuel elements |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US3294492A (en:Method) |
| BE (1) | BE688503A (en:Method) |
| DE (1) | DE1533142C3 (en:Method) |
| GB (1) | GB1142497A (en:Method) |
| SE (1) | SE311049B (en:Method) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3832439A (en) * | 1973-01-10 | 1974-08-27 | Atomic Energy Commission | Method for the suppression of hydrogen during the dissolution of zirconium and zirconium alloys |
| DE2613537A1 (de) * | 1976-03-30 | 1977-10-13 | Wiederaufarbeitung Von Kernbre | Verfahren zur konditionierung von metallischen, aus zirkonium oder zirkoniumlegierungen bestehenden huelsenabfaellen aus der aufarbeitung bestrahlter kernreaktor-brennelemente zur umweltschuetzenden endlagerung |
| US7566369B2 (en) * | 2001-09-14 | 2009-07-28 | Aleris Aluminum Koblenz Gmbh | Method of de-coating metallic coated scrap pieces |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB997355A (en) * | 1961-01-18 | 1965-07-07 | Atomenergi Ab | Improvements relating to the treatment of spent fuel elements from atomic reactors |
-
1966
- 1966-02-11 US US527383A patent/US3294492A/en not_active Expired - Lifetime
- 1966-09-05 GB GB39516/66A patent/GB1142497A/en not_active Expired
- 1966-10-19 BE BE688503D patent/BE688503A/xx unknown
- 1966-12-13 SE SE17097/66A patent/SE311049B/xx unknown
- 1966-12-19 DE DE1533142A patent/DE1533142C3/de not_active Expired
Also Published As
| Publication number | Publication date |
|---|---|
| SE311049B (en:Method) | 1969-05-27 |
| DE1533142A1 (de) | 1969-11-20 |
| DE1533142C3 (de) | 1975-01-09 |
| US3294492A (en) | 1966-12-27 |
| BE688503A (en:Method) | 1967-03-31 |
| DE1533142B2 (de) | 1974-05-30 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| ES347196A2 (es) | Procedimiento de regeneracion de combustibles para reacto- res nucleares irradiados. | |
| GB962779A (en) | Process for the preparation of uranium oxyfluoride and oxides of uranium therefrom | |
| DE3780825D1 (de) | Verfahren zur herstellung von urandioxid aus uranhexafluorid. | |
| SE8008447L (sv) | Konvertering av uranhexafluorid till uranoxider | |
| YU193884A (en) | Process for obtaining powder metal oxides from water solutions or solid metal oxides mixtures | |
| GB847013A (en) | Fuel element composition and process of making same | |
| GB1142497A (en) | A process for recovering uranium from zirconium clad uranium bearing nuclear fuel elements | |
| CA976363A (en) | Co-extraction and separate recovery of uranium and thorium from acid solutions | |
| GB1330535A (en) | Processing of irradiated nuclear reactor fuel | |
| GB1219528A (en) | Fluoride reprocessing of nuclear fuels | |
| GB1068969A (en) | Method of separation of uranium from plutonium | |
| GB1073000A (en) | Method for the reprocessing of uranium-containing nuclear fuels | |
| GB1021413A (en) | Pyrolytic carbon decladding of nuclear fuel | |
| GB1260096A (en) | Organic phase reduction of uranium | |
| GB1158287A (en) | Method of Fluorination of Nuclear Fuel. | |
| JPH0634057B2 (ja) | Mox燃料の製造方法 | |
| GB1010558A (en) | Extracting uranium values | |
| GB967568A (en) | Fluorination of oxidic nuclear fuel | |
| GB1205169A (en) | Improvements in or relating to the processing or irradiated nuclear fuel | |
| GB1170128A (en) | Method of Separating Actinides from Admixture and/or Various Actinides from each other during Reprocessing Spent Nuclear Fuels. | |
| Hoekstra | Phase Relationships in the Uranium-Oxygen and Binary Oxide Systems | |
| GB1536335A (en) | Uranium plutonium and neptunium(iv)sulphite tetrahydrates their preparation and a process for the preparation of an actinide dioxide | |
| GB953977A (en) | Method for preparing uo compacts | |
| GB1136060A (en) | Preparation of actinide sols by amine extraction | |
| FR2011952A2 (en) | Uranium dioxide prodn |