Using small x-ray beams to understand corrosion in nuclear fuel cladding

Arthur T. Motta, Aylin Yilmazbayhan, Robert J. Comstock, Barry Lai, Zhonghou Cai

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

Uniform oxidation by the primary circuit water and associated may soon limit the service of Zr alloy fuel cladding in Light Water reactors. Understanding the differences in corrosion rate between alloys based on the microstructure of the protective oxide may allow us to design better alloying materials for severe duty cycle applications. The use of synchrotron radiation microbeam at APS allows the study of these oxide layers with an unique combination of the wealth of diffraction and fluorescence information and the level of spatial resolution obtained. We will discuss some of our experimental results and the potentials of these techniques in solving engineering problems.

Original languageEnglish (US)
Title of host publicationApplications of X-Rays in Mechanical Engineering 2004
Pages103-114
Number of pages12
StatePublished - Dec 1 2004
Event2004 ASME International Mechanical Engineering Congress and Exposition, IMECE 2004 - Anaheim, CA, United States
Duration: Nov 13 2004Nov 19 2004

Publication series

NameApplications of X-Rays in Mechanical Engineering 2004

Other

Other2004 ASME International Mechanical Engineering Congress and Exposition, IMECE 2004
CountryUnited States
CityAnaheim, CA
Period11/13/0411/19/04

All Science Journal Classification (ASJC) codes

  • Engineering(all)

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  • Cite this

    Motta, A. T., Yilmazbayhan, A., Comstock, R. J., Lai, B., & Cai, Z. (2004). Using small x-ray beams to understand corrosion in nuclear fuel cladding. In Applications of X-Rays in Mechanical Engineering 2004 (pp. 103-114). [IMECE2004-62475] (Applications of X-Rays in Mechanical Engineering 2004).