Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1500420 | Scripta Materialia | 2009 | 4 Pages |
Abstract
Zirconium is widely used as fuel cladding material in nuclear power reactors. Here, a thermomechanical processing technique has been developed and implemented to improve the mechanical properties of commercially pure Zr-702. In the process the twin density increased to 45 areal%. The twins were identified to be mostly of {101¯2}〈101¯1¯〉 tensile twins or {101¯1}〈101¯2〉 compression twins. The significant increase in hardness was analyzed for its contributing factors and was attributed to the microstructural refinement caused by twin boundaries.
Related Topics
Physical Sciences and Engineering
Materials Science
Ceramics and Composites
Authors
J.H. Chung,