In-pile loop investigations of corrosion of Zircaloy-2 and other possible reactor materials in 0.04 m UO₂SO₄ at 280°C /

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Bibliographic Details
Main Author: Jenks, G. H. (Glenn Herbert), 1916-
Corporate Authors: U.S. Atomic Energy Commission, Oak Ridge National Laboratory
Other Authors: Baker, J. E.
Format: Government Document Book
Language:English
Published: Oak Ridge, Tenn. : Oak Ridge National Laboratory, [1960]
Series:ORNL (Series) ; 2962.
TID ; 4500 17th ed.
UC (Series). Metals, Ceramics, and Materials.
Subjects:

University of Minnesota

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Call Number: Y 3.AT 7:22/ORNL-2962