Method of manufacturing a nuclear fuel pellet by recycling an irradiated oxide fuel pellet
US6251310A · kind A · utility
Assignees
Inventors
Key dates
| Filing date | Nov 30, 1998 |
| Grant date | Jun 26, 2001 |
| Priority date | — |
| Expiry date | Nov 30, 2018 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
A method of manufacturing new UO.sub.2 -based fuel pellets by recycling irradiated UO.sub.2 -based fuel pellets. Irradiated UO.sub.2 -based fuel pellets are oxidized so as to make U.sub.3 O.sub.8 -based powder, and then the U.sub.3 O.sub.8 -based powder is mixed with an additive which contains at least one oxide of an element selected from the group consisting of niobium, titanium, vanadium, aluminum, magnesium, chromium, silicon and lithium. Green pellets are formed from the mixed powder, and then sintered, preferably at 1500.degree. C. or higher, in a reducing gas atmosphere to produce UO.sub.2 -based fuel pellets with high densities.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.