Date of Award:
5-2016
Document Type:
Thesis
Degree Name:
Master of Science (MS)
Department:
Mechanical and Aerospace Engineering
Committee Chair(s)
Heng Ban
Committee
Heng Ban
Committee
Thomas H. Fronk
Committee
Nicholas A. Roberts
Committee
Douglas E. Burkes
Abstract
Nuclear fuel characterization requires understanding of the various conditions to which materials are exposed in-reactor. One of these important conditions is corrosion, particularly that of fuel constituents. Therefore, corrosion behavior is of special interest and an essential part of nuclear materials characterization efforts. In support of the Office of Material Management and Minimization’s Reactor Conversion Program, monolithic uranium-10 wt% molybdenum alloy (UMo) is being investigated as a low enriched uranium alternative to highly enriched uranium dispersion fuel currently used in domestic high performance research reactors. The aqueous corrosion behavior of U-Mo is being examined at Pacific Northwest National Laboratory (PNNL) as part of U-Mo fuel fabrication capability activity. No prior study adequately represents this behavior given the current state of alloy composition and thermomechanical processing methods, and research reactor water chemistry.
Two main measurement techniques were employed to evaluate U-Mo corrosion behavior. Low-temperature corrosion rate values were determined by means of U-Mo immersion testing and subsequent mass-loss measurements. The electrochemical behavior of each processing condition was also qualitatively examined using the techniques of corrosion potential and anodic potentiodynamic polarization. Scanning electron microscopy (SEM) and optical metallography (OM) imagery and hardness measurements provided supplemental corrosion analysis in an effort to relate material corrosion behavior to processing.
The processing effects investigated as part of this were those of homogenization heat treatment (employed to mitigate the effects of coring in castings) and sub-eutectoid heat treatment, meant to represent additional steps in fabrication (such as hot isostatic pressing) performed at similar temperatures.
Immersion mass loss measurements and electrochemical results both showed very little appreciable difference between specimens of different process parameters. Comparative results were presented as linear corrosion rates and temperature-dependent Arrhenius equations, which were then correlated with electrochemical and metallographic findings for each condition under investigation.
This thesis was prepared in the monograph style using the ASME reference format.
Checksum
50f755a1f7d74441f3ff04ad7d8c4305
Recommended Citation
Gardner, Levi D., "Low-Temperature Aqueous Corrosion Behavior of Uranium Molybdenum Alloys" (2016). All Graduate Theses and Dissertations, Spring 1920 to Summer 2023. 4755.
https://digitalcommons.usu.edu/etd/4755
Included in
Copyright for this work is retained by the student. If you have any questions regarding the inclusion of this work in the Digital Commons, please email us at .