Open AccessThermal Analysis of Repository Codisposal Waste Packages Containing Melt-Dilute Aluminum Spent Nuclear Fuel
Author(s) -
S.Y. Lee
Publication year - 1999
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/14493
Subject(s) - spent nuclear fuel , thermal conduction , decay heat , nuclear engineering , radioactive waste , thermal , convection , materials science , waste management , environmental science , thermodynamics , engineering , composite material , physics
The engineering viability of disposal of aluminum-clad, aluminum-based spent nuclear fuel in a geologic repository requires a thermal analysis to provide the temperature history of the waste form
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