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...
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 |
Similar Items
-
Research on Thermal Stability and Properties of Ca<sub>3</sub>ZrSi<sub>2</sub>O<sub>9</sub> as Potential T/EBC Materials
by: Yangyang Pan, et al.
Published: (2021-05-01) -
Mechanical analysis of surface-coated zircaloy cladding
by: Youho Lee, et al.
Published: (2017-08-01) -
Microstructural, mechanical properties and high temperature oxidation of Cr, Al-coated Zr-4 alloy
by: Jinghao Huang, et al.
Published: (2020-12-01) -
Microstructural characterization of accident tolerant fuel cladding with Cr–Al alloy coating layer after oxidation at 1200 °C in a steam environment
by: Dong Jun Park, et al.
Published: (2020-10-01) -
STUDY OF THERMAL CREEP OF COATED CLADDING MATERIALS
by: Martin Ševeček, et al.
Published: (2018-12-01)