GB2020641A - Nuclear fuel pellets containing niobium pentoxide - Google Patents
Nuclear fuel pellets containing niobium pentoxideInfo
- Publication number
- GB2020641A GB2020641A GB7915141A GB7915141A GB2020641A GB 2020641 A GB2020641 A GB 2020641A GB 7915141 A GB7915141 A GB 7915141A GB 7915141 A GB7915141 A GB 7915141A GB 2020641 A GB2020641 A GB 2020641A
- Authority
- GB
- United Kingdom
- Prior art keywords
- sintering
- oxides
- nuclear fuel
- niobium pentoxide
- fuel pellets
- 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.)
- Granted
Links
- 239000008188 pellet Substances 0.000 title abstract 3
- ZKATWMILCYLAPD-UHFFFAOYSA-N niobium pentoxide Inorganic materials O=[Nb](=O)O[Nb](=O)=O ZKATWMILCYLAPD-UHFFFAOYSA-N 0.000 title abstract 2
- URLJKFSTXLNXLG-UHFFFAOYSA-N niobium(5+);oxygen(2-) Chemical compound [O-2].[O-2].[O-2].[O-2].[O-2].[Nb+5].[Nb+5] URLJKFSTXLNXLG-UHFFFAOYSA-N 0.000 title abstract 2
- 239000003758 nuclear fuel Substances 0.000 title abstract 2
- 238000005245 sintering Methods 0.000 abstract 5
- 239000000843 powder Substances 0.000 abstract 3
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 abstract 1
- 229910052778 Plutonium Inorganic materials 0.000 abstract 1
- 229910052776 Thorium Inorganic materials 0.000 abstract 1
- 229910052770 Uranium Inorganic materials 0.000 abstract 1
- QVGXLLKOCUKJST-UHFFFAOYSA-N atomic oxygen Chemical compound [O] QVGXLLKOCUKJST-UHFFFAOYSA-N 0.000 abstract 1
- 239000012535 impurity Substances 0.000 abstract 1
- 238000004519 manufacturing process Methods 0.000 abstract 1
- 239000011159 matrix material Substances 0.000 abstract 1
- 238000000034 method Methods 0.000 abstract 1
- 239000000203 mixture Substances 0.000 abstract 1
- 229910052760 oxygen Inorganic materials 0.000 abstract 1
- 239000001301 oxygen Substances 0.000 abstract 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 abstract 1
- 238000003825 pressing Methods 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
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- 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)
- Physics & Mathematics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
In the production of nuclear fuel pellets consisting essentially of oxides of uranium or mixtures of these oxides with oxides of thorium or plutonium by granulating the oxide powder, pressing the granulated powder into compacts and sintering the compacts, niobium pentoxide is added to the oxide powder in sufficient quantity to encourage grain growth in the oxide compact during sintering and the sintering and other process parameters are adjusted so that no impurities are trapped in the sintering pellets which would prevent a high matrix density and grain size being obtained. Adjustment and control of the oxygen potential of the sintering atmosphere is proposed.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB7915141A GB2020641B (en) | 1978-05-15 | 1979-05-01 | Nuclear fuel pellets containing niobium pentoxide |
| IT68021/79A IT1166452B (en) | 1978-05-15 | 1979-05-14 | PROCEDURE FOR THE PRODUCTION OF NUCLEAR FUEL TABS |
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB1963578 | 1978-05-15 | ||
| GB7915141A GB2020641B (en) | 1978-05-15 | 1979-05-01 | Nuclear fuel pellets containing niobium pentoxide |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB2020641A true GB2020641A (en) | 1979-11-21 |
| GB2020641B GB2020641B (en) | 1982-10-13 |
Family
ID=26254157
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB7915141A Expired GB2020641B (en) | 1978-05-15 | 1979-05-01 | Nuclear fuel pellets containing niobium pentoxide |
Country Status (2)
| Country | Link |
|---|---|
| GB (1) | GB2020641B (en) |
| IT (1) | IT1166452B (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0076680A1 (en) * | 1981-10-02 | 1983-04-13 | Westinghouse Electric Corporation | Stable UO2 fuel pellets |
| GB2255085A (en) * | 1991-04-17 | 1992-10-28 | British Nuclear Fuels Plc | Manufacture of sintered uranium dioxide |
| GB2330685A (en) * | 1997-10-25 | 1999-04-28 | British Nuclear Fuels Plc | Production of plutonium containing products |
| US10361008B2 (en) | 2014-09-08 | 2019-07-23 | Westinghouse Electric Sweden Ab | Method of making a nuclear fuel pellet for a nuclear power reactor |
-
1979
- 1979-05-01 GB GB7915141A patent/GB2020641B/en not_active Expired
- 1979-05-14 IT IT68021/79A patent/IT1166452B/en active
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0076680A1 (en) * | 1981-10-02 | 1983-04-13 | Westinghouse Electric Corporation | Stable UO2 fuel pellets |
| GB2255085A (en) * | 1991-04-17 | 1992-10-28 | British Nuclear Fuels Plc | Manufacture of sintered uranium dioxide |
| US5211905A (en) * | 1991-04-17 | 1993-05-18 | British Nuclear Fuels Plc | Manufacture of sintered uranium dioxide |
| GB2255085B (en) * | 1991-04-17 | 1994-11-16 | British Nuclear Fuels Plc | Manufacture of sintered uranium dioxide |
| GB2330685A (en) * | 1997-10-25 | 1999-04-28 | British Nuclear Fuels Plc | Production of plutonium containing products |
| US10361008B2 (en) | 2014-09-08 | 2019-07-23 | Westinghouse Electric Sweden Ab | Method of making a nuclear fuel pellet for a nuclear power reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| IT7968021A0 (en) | 1979-05-14 |
| GB2020641B (en) | 1982-10-13 |
| IT1166452B (en) | 1987-05-06 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US3011960A (en) | Methods of manufacturing graphite bodies and nuclear fuel materials comprising said graphite bodies | |
| ES480546A1 (en) | Production of nuclear fuel pellets | |
| ES8405548A1 (en) | Burnable neutron absorbers. | |
| US3806565A (en) | Method of preparing relatively low density oxide fuel for a nuclear reactor | |
| GB1148478A (en) | Process for manufacturing sintered pellets of nuclear fuel | |
| GB1507878A (en) | Mixed oxide nuclear fuel | |
| US4512939A (en) | Method for manufacturing oxidic sintered nuclear fuel bodies | |
| ES473401A1 (en) | Method of producing PuO2/UO2/-nuclear fuels | |
| GB2020641A (en) | Nuclear fuel pellets containing niobium pentoxide | |
| US3375306A (en) | Method of producing dense,sintered bodies of uo2 or uo2-puo2 mixtures | |
| US3114689A (en) | Ceramic fuel for nuclear reactors | |
| GB1285190A (en) | Improvements in ceramic fissile materials | |
| GB982926A (en) | Coherent nuclear materials and reactor elements made therefrom | |
| GB1128742A (en) | Nuclear fuel element and method of fabricating of said element | |
| US3761546A (en) | Method of making uranium dioxide bodies | |
| GB1471811A (en) | Nuclear fuel pellets | |
| CA1169643A (en) | Method for producing mixed-oxide nuclear fuel pellets soluble in nitric acid | |
| GB1397014A (en) | Fabrication process for nuclear fuel pellets | |
| GB1371595A (en) | Manufacturing process for mixed nuclear fuel pellets | |
| GB1182080A (en) | Nuclear Fuel | |
| GB1030465A (en) | Method of preparation of mixed oxides of actinides | |
| JPS6479691A (en) | Manufacture of mox fuel | |
| US3362914A (en) | Uranium carbide-plutonium phosphide as a reactor fuel | |
| US3356776A (en) | Method of fabricating ceramic nuclear fuel product | |
| GB960352A (en) | Improvements in or relating to the fabrication of fuel elements and elements so produced |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PE20 | Patent expired after termination of 20 years |
Effective date: 19990430 |