GB1226198A - - Google Patents
Info
- Publication number
- GB1226198A GB1226198A GB1226198DA GB1226198A GB 1226198 A GB1226198 A GB 1226198A GB 1226198D A GB1226198D A GB 1226198DA GB 1226198 A GB1226198 A GB 1226198A
- Authority
- GB
- United Kingdom
- Prior art keywords
- dissolved
- melt
- dec
- precipitate
- carbide
- 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
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 abstract 6
- 239000000446 fuel Substances 0.000 abstract 2
- 229910052783 alkali metal Inorganic materials 0.000 abstract 1
- 150000001339 alkali metal compounds Chemical class 0.000 abstract 1
- 150000001340 alkali metals Chemical class 0.000 abstract 1
- YZUCHPMXUOSLOJ-UHFFFAOYSA-N ethyne;thorium Chemical compound [Th].[C-]#[C] YZUCHPMXUOSLOJ-UHFFFAOYSA-N 0.000 abstract 1
- 238000003682 fluorination reaction Methods 0.000 abstract 1
- KAQHZJVQFBJKCK-UHFFFAOYSA-L potassium pyrosulfate Chemical compound [K+].[K+].[O-]S(=O)(=O)OS([O-])(=O)=O KAQHZJVQFBJKCK-UHFFFAOYSA-L 0.000 abstract 1
- 239000002244 precipitate Substances 0.000 abstract 1
- 239000007787 solid Substances 0.000 abstract 1
- 239000002915 spent fuel radioactive waste Substances 0.000 abstract 1
- ZCUFMDLYAMJYST-UHFFFAOYSA-N thorium dioxide Chemical compound O=[Th]=O ZCUFMDLYAMJYST-UHFFFAOYSA-N 0.000 abstract 1
- 229910003452 thorium oxide Inorganic materials 0.000 abstract 1
- SANRKQGLYCLAFE-UHFFFAOYSA-H uranium hexafluoride Chemical class F[U](F)(F)(F)(F)F SANRKQGLYCLAFE-UHFFFAOYSA-H 0.000 abstract 1
- 229910000439 uranium oxide Inorganic materials 0.000 abstract 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/44—Reprocessing of irradiated fuel of irradiated solid fuel
- G21C19/48—Non-aqueous processes
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/04—Halides of uranium
- C01G43/06—Fluorides
- C01G43/063—Hexafluoride (UF6)
- C01G43/066—Preparation
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
1,226,198. Uranium fluorides. KERN FORSCHUNGSANLAGE JULICH G.m.b.H.. 20 Dec., 1968 [21 Dec., 1967], No. 60610/68. Heading C1A. [Also in Division G6] Spent nuclear fuel containing uranium and thorium oxide or carbide is dissolved in an alkali metal compound melt, and the solution is treated to precipitate an alkali metal uranate which is separated and fluorinated to form UF 6. In one embodiment, oxide fuel is dissolved in potassium pyrosulphate melt and solid NaOH is added to form the precipitate; in another embodiment, carbide fuel is dissolved in a NaOH » Na 2 O 2 or a Na 2 CO 3» K 2 CO 3 melt. Fluorination to UF 6 is carried out in a fluidized bed (a) with HF to form UO 2 F 2 and then with F 2 ; (b) with HF mixed with S0 2 or NH 3 to form UF 4 and then with F 2 ; or (c) directly with F 2 .
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19671592129 DE1592129C (en) | 1967-12-21 | 1967-12-21 | Process for the reprocessing of nuclear fuel elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1226198A true GB1226198A (en) | 1971-03-24 |
Family
ID=5680233
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1226198D Expired GB1226198A (en) | 1967-12-21 | 1968-12-20 |
Country Status (2)
Country | Link |
---|---|
FR (1) | FR1596241A (en) |
GB (1) | GB1226198A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO1996032729A1 (en) * | 1995-04-12 | 1996-10-17 | British Nuclear Fuels Plc | Method of processing oxide nuclear fuel |
GB2341396A (en) * | 1998-09-11 | 2000-03-15 | Toshiba Kk | Molten salt electrolysis of nuclear waste |
-
1968
- 1968-12-20 FR FR1596241D patent/FR1596241A/fr not_active Expired
- 1968-12-20 GB GB1226198D patent/GB1226198A/en not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO1996032729A1 (en) * | 1995-04-12 | 1996-10-17 | British Nuclear Fuels Plc | Method of processing oxide nuclear fuel |
GB2341396A (en) * | 1998-09-11 | 2000-03-15 | Toshiba Kk | Molten salt electrolysis of nuclear waste |
GB2341396B (en) * | 1998-09-11 | 2001-05-23 | Toshiba Kk | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
US6299748B1 (en) | 1998-09-11 | 2001-10-09 | Kabushiki Kaisha Toshiba | Method and apparatus of treating waste from nuclear fuel handling facility |
US6736951B2 (en) | 1998-09-11 | 2004-05-18 | Kabushiki Kaisha Toshiba | Method of treating waste from nuclear fuel handling facility and apparatus for carrying out the same |
Also Published As
Publication number | Publication date |
---|---|
DE1592129B2 (en) | 1972-08-24 |
DE1592129A1 (en) | 1972-03-09 |
FR1596241A (en) | 1970-06-15 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed [section 19, patents act 1949] | ||
PCNP | Patent ceased through non-payment of renewal fee |