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Survey of End Capping Methods for Zircaloy-2-Clad Uranium Fuel Elements
From Abstract: "A literature survey was made of both welding and brazing methods that might be used to minimize the amount of exposed core material and provide the longest path for corrosion in the event of a defective weld in enextruded Zircaloy-2-clad uranium and uranium-2 w/o zirconium fuel elements."
Date:
October 27, 1959
Creator:
Vagi, Julius J.; Koppenhofer, Roger L. & Evans, Robert M.
System:
The UNT Digital Library
Maritime Organic Moderated and Cooled Reactor
Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date:
May 27, 1959
Creator:
unknown
System:
The UNT Digital Library