Aqueous Corrosion of Uranium Fuel-Element Cores Containing 0 to 20 w/o Zirconium (open access)

Aqueous Corrosion of Uranium Fuel-Element Cores Containing 0 to 20 w/o Zirconium

Abstract: A description is given of the design and operation of a windowed autoclave system employed in the study of corrosion by pressurized hot water. The device has been used to obtain time-lapse motion pictures of the swelling and rupture of deliberately defected zirconium-clad uranium specimens. A method is described by which corrosion rates were calculated from pressure and temperature measurements. A typical set of pictures taken during a test is presented, and corrosion rates are reported for uranium-0, 5, 10, 15, and 20 w/o zirconium alloys subjected subjected to 600 F water.
Date: January 7, 1957
Creator: Grieser, Daniel R. & Simons, Eugene M.
System: The UNT Digital Library
Characterization of Inclusion in Dingot Uranium (open access)

Characterization of Inclusion in Dingot Uranium

Abstract: The nonmetallic inclusions in both as-reduced and fabricated dingot uranium have been studied for comparison with those in ingot uranium. Special attention was paid to the hydride for the purpose of determining the amount and distribution in the various types of uranium. The types and distribution of other inclusions were also studied. It was found that the dingot uranium was of a higher quality than ingot uranium and was comparable to as-reduced derby uranium on the basis of over-all inclusion count. The hydrogen content in dingot uranium, however, was found to be appreciably higher than in either ingot or derby uranium.
Date: January 11, 1957
Creator: Cheney, Donald M. & Dickerson, Ronald F.
System: The UNT Digital Library