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Critical Review of the Thermophysical Properties of Fast‐Reactor Fuel
Author(s) -
FINK J. K.
Publication year - 1985
Publication title -
journal of the american ceramic society
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.9
H-Index - 196
eISSN - 1551-2916
pISSN - 0002-7820
DOI - 10.1111/j.1151-2916.1985.tb09652.x
Subject(s) - actinide , thermal conductivity , materials science , nuclear engineering , nuclear fuel , solid fuel , thermodynamics , chemical engineering , chemistry , nuclear chemistry , composite material , engineering , physics , combustion
This paper identifies the fuel properties for which more data are needed for fast‐reactor safety analysis. In addition, a brief review is given of current research on the vapor pressure over liquid UO 2 and (U, Pu)O 2‐x the solid‐solid phase transition in actinide oxides, and the thermal conductivity of molten urania.