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In-Pile Loop Investigations of Corrosion of Zircaloy-2 and Other Possible Reactor Materials in 0.04 m UO2SO4 AT 280°C
One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.
Date:
May 5, 1962
Creator:
Jenks, G. H.
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Preliminary Safeguards Analysis
Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.
Date:
June 5, 1958
Creator:
Wittenbrock, N. G.
System:
The UNT Digital Library