GB1356766A - Production of materials for use as nuclear fuels - Google Patents
Production of materials for use as nuclear fuelsInfo
- Publication number
- GB1356766A GB1356766A GB1896272A GB1896272A GB1356766A GB 1356766 A GB1356766 A GB 1356766A GB 1896272 A GB1896272 A GB 1896272A GB 1896272 A GB1896272 A GB 1896272A GB 1356766 A GB1356766 A GB 1356766A
- Authority
- GB
- United Kingdom
- Prior art keywords
- materials
- production
- pyrohydrolysis
- reduction
- nuclear fuels
- 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
Classifications
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
- C01G43/01—Oxides; Hydroxides
- C01G43/025—Uranium dioxide
-
- C—CHEMISTRY; METALLURGY
- C01—INORGANIC CHEMISTRY
- C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
- C01P2006/00—Physical properties of inorganic compounds
- C01P2006/80—Compositional purity
Landscapes
- Chemical & Material Sciences (AREA)
- Organic Chemistry (AREA)
- Life Sciences & Earth Sciences (AREA)
- General Life Sciences & Earth Sciences (AREA)
- Geology (AREA)
- Inorganic Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1356766 Oxide purification RBG REAKTORBRENNELEMENTE GmbH 24 April 1972 [1 June 1971] 18962/72 Heading C1A The fluoride content of powdered oxides of nuclear fuel elements is reduced by pyrohydrolysis with steam in the absence of H 2 . The oxide is preferably UO 2 formed by reduction of UO 3 with H 2 , and the pyrohydrolysis may be carried out in the same reactor as reduction or in a separate reactor. The preferred temperature is greater than 650‹ C., e.g. 680‹ C., and the final F content may be less than 25 p.p.m.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE2127107A DE2127107C3 (en) | 1971-06-01 | 1971-06-01 | Process for the depletion of fluoride ions from UO2 powders |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1356766A true GB1356766A (en) | 1974-06-12 |
Family
ID=5809487
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1896272A Expired GB1356766A (en) | 1971-06-01 | 1972-04-24 | Production of materials for use as nuclear fuels |
Country Status (7)
Country | Link |
---|---|
BE (1) | BE784111A (en) |
DE (1) | DE2127107C3 (en) |
FR (1) | FR2140100B1 (en) |
GB (1) | GB1356766A (en) |
IT (1) | IT955890B (en) |
SE (1) | SE400272B (en) |
ZA (1) | ZA723707B (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2724954C2 (en) * | 1977-06-02 | 1984-11-15 | Reaktor-Brennelement Union Gmbh, 6450 Hanau | Process for the decontamination of alpha and beta-active process water |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE1592471C3 (en) * | 1966-04-02 | 1978-11-30 | Nukem Gmbh, 6450 Hanau | Process for the production of uranium dioxide powders and granules |
-
1971
- 1971-06-01 DE DE2127107A patent/DE2127107C3/en not_active Expired
-
1972
- 1972-04-24 GB GB1896272A patent/GB1356766A/en not_active Expired
- 1972-05-26 IT IT24894/72A patent/IT955890B/en active
- 1972-05-29 BE BE784111A patent/BE784111A/en not_active IP Right Cessation
- 1972-05-29 SE SE7207019A patent/SE400272B/en unknown
- 1972-05-30 ZA ZA723707A patent/ZA723707B/en unknown
- 1972-05-30 FR FR7219379A patent/FR2140100B1/fr not_active Expired
Also Published As
Publication number | Publication date |
---|---|
DE2127107C3 (en) | 1978-10-12 |
DE2127107A1 (en) | 1973-01-04 |
ZA723707B (en) | 1973-12-19 |
FR2140100B1 (en) | 1977-12-23 |
DE2127107B2 (en) | 1978-02-16 |
IT955890B (en) | 1973-09-29 |
BE784111A (en) | 1972-09-18 |
FR2140100A1 (en) | 1973-01-12 |
SE400272B (en) | 1978-03-20 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
AU469610B2 (en) | Improvements in or relating to fuel assembly fora nuclear reactor | |
GB1394235A (en) | Chemical immobilization of fission products reactive with nuclear reactor components | |
AU463432B2 (en) | Improvements in or relating to nuclear reactor fuel element assemblies | |
CA1010162A (en) | Reducing concentration of gases in nuclear reactor | |
AU464042B2 (en) | Improvements in or relating to nuclear reactor fuel element assemblies | |
ZA724474B (en) | Improvements in or relating to nuclear reactor fuel elements | |
GB1350923A (en) | Method for preparing oxides of fissile materials | |
AU466313B2 (en) | Improvements in or relating to nuclear reactor fuel element assemblies | |
GB1356766A (en) | Production of materials for use as nuclear fuels | |
GB1365014A (en) | Ceramic defluorination and reduction process | |
CA977544A (en) | Method for reducing the oxygen in certain actinide oxides to less than stoichiometric levels | |
GB1335588A (en) | Fluidized bed production of uranium monocarbide and uranium monocarbide-uranium aluminide mixtures | |
GB1366923A (en) | Production of nuclear fuel | |
GB1329344A (en) | Continuous process for the preparation of oxide of uranium oxide of uranium-oxide of plutonium spheres with a controlled porosity | |
GB1228654A (en) | ||
GB1241976A (en) | Process for preparing sintered pellets of ceramic materials to be used as nuclear fuels and products obtained by the process | |
GB1375371A (en) | ||
GB1129855A (en) | Method for fluoridation of nuclear fuel by means of gaseous chlorine trifluoride | |
GB844833A (en) | Nuclear reactor fuel preparation | |
AU491060B2 (en) | Improvements in or relating to nuclear reactor fuel elements | |
CA864150A (en) | Nuclear reactor fuel elements | |
CA862728A (en) | Process of finishing parts of zirconium alloys such as for use with nuclear reactor plants | |
AU8387475A (en) | Improvements in or relating to nuclear reactor fuel elements | |
GB1137663A (en) | Oxidation catalysts and methods for their preparation | |
AU458399B2 (en) | Actinide nitride fueled reactor and continuous method of operating same |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |