
Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets“Fast Reactor Fuel (Withdrawn 2014)
STANDARD published on 1.1.2008
Designation standards: ASTM C1008-99(2008)
Note: WITHDRAWN
Publication date standards: 1.1.2008
The number of pages: 4
Approximate weight : 12 g (0.03 lbs)
Country: American technical standard
Category: Technical standards ASTM
Keywords:
breeder reactor, fast reactor, mixed oxide fuels, nuclear fuel, nuclear fuel pellets, plutonium, uranium, Breeder reactor core components, Mixed oxides (MOX), Nuclear fuels (reactor)--specifications, Nuclear materials/applications--specifications, Nuclear reactor vessels, Plutonium, Uranium--specifications, Uranium-plutonium dioxide pellets (sintered), ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)