Hydride reorientation in zirconium alloy nuclear fuel cladding studied using synchrotron radiation [electronic resource] / Jennifer Anne Jarvis
- During reactor operation, waterside corrosion of Zirconium alloy fuel cladding leads to hydrogen pickup. Hydrides platelets will normally precipitate circumferentially in the cladding. However, under temperature and load, the hydrides can reorient in the radial direction. These brittle radial hydrides can drastically reduce the ductility and the fracture toughness of the cladding. This work contains an in-situ study of hydride reorientation. Using synchrotron radiation from the Advanced Photon Source (APS) at Argonne National Laboratory, x-ray diffraction in transmission geometry was used to study a hydrogen-charged sample under mechanical and thermal load. The sample was rolled Zircaloy-2 with a hydrogen content of 96 wt.ppm. It was studied under a loading cycle with temperature cycling from 25 to 400°C and with an applied tensile stress of 100 MPa. Under two cycles of loading, partial reorientation was achieved. This diffraction data was used to perform an evaluation of the intensity, peak broadening, and peak shift of hydride peaks, in order to characterize the kinetics of reorientation. Additionally, the dissolution and precipitation temperatures were studied. Optical microscopy was used to compare the microstructure and hydride orientation before and after the experiment.
- Dissertation Note:
- B.S. Pennsylvania State University 2010.
- Mode of access: World Wide Web. and Thesis supervisor: Arthur Motta, Kimberly Colas.
- Reproduction Note:
- Library holds archival microfiche negative and service copy. 1 fiche. (PSU Management Services, 2010).
- Technical Details:
- The full text of the dissertation is available as a Adobe Acrobat .pdf file ; Adobe Acrobat Reader required to view the file.
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