Open AccessConsolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins
Author(s) -
M.L. Batch,
N.L. Snidow
Publication year - 1960
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4110238
Subject(s) - thorium , oxide , nuclear engineering , nuclear reactor core , materials science , core (optical fiber) , mox fuel , metallurgy , engineering , composite material , uranium
Critical experiments with pin-type oxide fuel elements for the CETR are described. These experiments were conducted to provide data on the infinite medium properties of the lattice inside the canned elements in the various CETR loading zones and to obtain specific information on the fullsize CETR core. Measurements are described and results are interpreted. (J.R.D.
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