Fracture toughness of hydrided zircaloy-4 sheet under through-thickness crack growth conditions

P. A. Raynaud, D. A. Koss, A. T. Motta, K. S. Chan

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

7 Scopus citations


The susceptibility of fuel cladding to failure in the case of a postulated reactivity-initiated accident may be determined by crack initiation within a hydride blister or rim and subsequent crack growth through the thickness of the cladding. This study has determined the fracture toughness of hydrided cold-worked stress relieved Zircaloy-4 sheet subject to through-thickness crack growth at both 25 and 300°C. The experimental approach utilizes a novel procedure in which a narrow linear strip of brittle hydride blister across the specimen width creates a well-defined precrack upon initial loading. The subsequent crack growth resistance is then characterized by four-point bending of the specimen and an elastic-plastic fracture mechanics analysis. At room temperature, the through-thickness fracture toughness (Kq) is sensitive to the orientation of the hydride platelets and Kq≅25 MPa√m for crack growth through a mixed in-plane/out-of-plane hydride field. In contrast, Kq is much higher (≅75 MPa√m) when the hydride platelets are oriented predominantly in the plane of the sheet and therefore normal to both the crack plane and the crack growth direction. At 300°C, the material exhibits greater ductility as the hydride particles within the matrix resist fracture such that Kq≅S3 MPa√m, despite the much lower flow stress of the material.

Original languageEnglish (US)
Title of host publicationZirconium in the Nuclear Industry
Subtitle of host publication15th International Symposium
PublisherAmerican Society for Testing and Materials
Number of pages16
ISBN (Print)9780803145146
StatePublished - 2009
Event15th International Symposium on Zirconium in the Nuclear Industry - Sunriver, OR, United States
Duration: Jun 24 2007Jun 28 2007

Publication series

NameASTM Special Technical Publication
Volume1505 STP
ISSN (Print)0066-0558


Other15th International Symposium on Zirconium in the Nuclear Industry
Country/TerritoryUnited States
CitySunriver, OR

All Science Journal Classification (ASJC) codes

  • General Materials Science


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