Patent · US Expired

Method of producing mixed-oxide nuclear fuel pellets soluble in nitric acid

US4676935A · kind A · utility

3Cited by
4References
1Claims
0Family size

Assignee

Inventors

Key dates

Filing dateSep 13, 1985
Grant dateJun 30, 1987
Priority date
Expiry dateSep 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.