Index Catalog // ScholarsArchive@OSU

Start Over

Filtering by: Subject Nuclear fuels Degree Field Materials Science

Characterization of Oxide Growth of Aluminum Alloy 6061 for Nuclear Research and Test Reactors

Creator:

Wei, Youran

Abstract:

Oxide growth is a common phenomenon on aluminum alloy cladding surfaces in nuclear research and test reactors. Without better understanding of oxide growth, excessive oxide build up on the cladding surface reduces heat transfer capability from fuel to coolant and causes safety concerns due to the potential cladding rupture or...

Resource Type:

Masters Thesis

Full Text:

Nuclear Research AN ABSTRACT OF THE THESIS OF Youran Wei for the degree of