Method of producing mixed-oxide nuclear fuel pellets soluble in

Details Method of producing mixed-oxide nuclear fuel pellets soluble in Method of producing mixed-oxide nuclear fuel pellets soluble in

1985-09-13

1987-06-30

Lovering, Richard D.

Plastic and nonmetallic article shaping or treating: processes

Shaping or treating radioactive material

252627, 252643, G21C 2100, G21C 1942, G21C 1944

Patent

active

046769358

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.

REFERENCES:
patent: 3087781 (1963-04-01), Levey et al.
patent: 3806565 (1974-04-01), Langrod
patent: 4247495 (1981-01-01), Ennerst et al.
patent: 4284593 (1981-08-01), Sutcliffe et al.
Gardner, "Uranium Dioxide and Other Ceramic Fuels" in Kaufmann, Ed. Nuclear Reactor Fuel Elements:Metallurgy and Fabrication, Interscience Publishers (1962) New York, pp. 200-203.
Sands et al., Powder Metallurgy:Practice and Applications, George Newnes Ltd., London (1966), pp. 24-25.

Affiliated with

Also associated with

Rating

Method of producing mixed-oxide nuclear fuel pellets soluble in does not yet have a rating. At this time, there are no reviews or comments for this patent.

If you have personal experience with Method of producing mixed-oxide nuclear fuel pellets soluble in , we encourage you to share that experience with our LandOfFree.com community. Your opinion is very important and Method of producing mixed-oxide nuclear fuel pellets soluble in will most certainly appreciate the feedback.

Rate now

Comments { 0 }

Profile ID: LFUS-PAI-O-446663