Hydride behavior in zircaloy-4 during thermomechanical cycling

Kimberly Colas, Arthur Motta, Mark R. Daymond, Jonathan Almer, Zhonghou Cai

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

1 Scopus citations

Abstract

Hydrogen ingress into zirconium alloy fuel cladding during operation in nuclear reactors can degrade cladding performance, both during operation and under dry storage, due to formation of brittle hydrides. At temperature and under stress, hydrogen redistribution and reorientation can occur, reducing cladding resistance to failure. Thus, it is crucial to understand the kinetics of hydride dissolution and re-orientation under stress and at temperature. High-energy and micro-beam synchrotron diffraction are used to study the kinetics of hydride reorientation and hydride distribution near a crack tip in previously hydrided Zircaloy sheet. Reorientation of hydrides in bulk samples is studied in situ (at temperature and under applied tensile stress). In-situ transmission diffraction data provides unique strain and orientation information on the hydrides. Micro-beam diffraction has been performed on previously cracked compact tension specimens under load. Measurement of the hydride distribution and associated strains can be performed with the micro-beam to determine hydrogen response to an applied strain field.

Original languageEnglish (US)
Title of host publication15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
PublisherJohn Wiley and Sons Inc.
Pages645-650
Number of pages6
ISBN (Print)9781622761944
StatePublished - Jan 1 2011
Event15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 - Colorado Springs, CO, United States
Duration: Aug 7 2011Aug 11 2011

Publication series

Name15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
Volume1

Other

Other15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011
CountryUnited States
CityColorado Springs, CO
Period8/7/118/11/11

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Pollution

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    Colas, K., Motta, A., Daymond, M. R., Almer, J., & Cai, Z. (2011). Hydride behavior in zircaloy-4 during thermomechanical cycling. In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 (pp. 645-650). (15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011; Vol. 1). John Wiley and Sons Inc..