High-temperature oxidation behaviors of ZrSi2 and its coating on the surface of Zircaloy-4 tube by laser 3D printing

The high-temperature oxidation behavior of ZrSi2 used as a coating material for nuclear fuel cladding was investigated for developing accident-tolerant fuel cladding of light water reactors. Bulk ZrSi2 samples were prepared by spark plasma sintering. In situ X-ray diffraction was conducted in air at...

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Bibliographic Details
Main Authors: Jae Joon Kim, Hyun Gil Kim, Ho Jin Ryu
Format: Article
Language:English
Published: Elsevier 2020-09-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S173857331930991X