Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid
US4676935A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Sep 13, 1985 |
| Grant date | Jun 30, 1987 |
| Priority date | — |
| Expiry date | Sep 13, 2005 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY02E30/30
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
Production of mixed-oxide nuclear fuel pellets of uranium dioxide (UO.sub.2+x) and plutonium dioxide (PuO.sub.2) which are soluble in nitric acid. The powder mixture of oxides is added to a halogen-free milling aid, such as propane diol, then is milled and subsequently granulated, pressed and sintered. The milling aid is expelled by subsequent drying processes or heat treatments (sintering). The milling process is controlled to obtain a primary grain size of less than two micrometers.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.