Tribological Behavior of Structural Materials in High Temperature Helium Gas-Cooled Reactor Environments CX(s) Applied: B3.6Date: 07/01/2016 Location(s): IdahoOffices(s): Nuclear Energy
Office of NEPA Policy and Compliance
July 1, 2016
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Tribological Behavior of Structural Materials in High Temperature Helium Gas-Cooled Reactor Environments
CX(s) Applied: B3.6
Date: 07/01/2016
Location(s): Idaho
Offices(s): Nuclear Energy
The project will investigate the wear mechanisms of surface treatments for alloys 800H and 617 will be investigated to: (i) mitigate tribological damage in High Temperature Gas Reactor (HTGR) environments, (ii) minimize sensitivity of corrosion to various impurity regimes and provide greater predictability in wear behavior, (iii) promote the formation of a mechanically stable oxide layer that would acquire a low friction glaze nanostructure during the high temperature wear process, and (iv) impede carbon diffusion into or out from the alloys (for carburizing and decarburizing environments, respectively).