Search U.S. government technical reports digitized or harvested by TRAIL.

Keyword Search

Effect of heat flux on the corrosion of aluminum by water.

Outgassing behavior of EGCR moderator graphite

Mechanical properties of X8001 and 6061 aluminum alloys and aluminum-base fuel dispersion at elevated temperatures

Mechanical cladding-fuel interactions during thermal cycling of metal-clad fuel elements

Published Year

• 1960-1969 (4) *

Subject

• Nuclear reactors--Materials--Testing (4) *
• Nuclear fuel claddings (2)
• Nuclear fuel elements (2)
• Aluminum alloys--Analysis (1)
• Aluminum--Corrosion (1)
• Corrosion and anti-corrosives (1)
• Dispersion (1)
• Gas cooled reactors (1)
• Graphite (1)
• Nuclear fuel claddings--Testing (1)
• Nuclear reactors--Corrosion (1)
• Outgassing (Low pressure environments) (1)
• Uranium dioxide (1)
• Water (1)

Author

• Martin, W. R. (2)
• Blakely, J. P. (1)
• English, J. L. (1)
• Griess, J. C. (1)
• Overholser, L. G. (1)
• Savage, H. C. (1)
• Weir, J. R. (1)

• About TRAIL
• FAQ
• Join TRAIL
• Contact Us

Search developed and maintained by the University of Washington Libraries
Copyright 2010