Effects of texture and microstructure on the propagation of iodine stress corrosion cracks in Zircaloy

Journal Article · Fri Jan 01 00:00:00 EST 1982 · Metall. Trans., A; (United States)

DOI:https://doi.org/10.1007/BF02642417· OSTI ID:5333311

Knorr, D B; Pelloux, R M

Failure of some fuel elements in light water nuclear reactors has been attributed to stress corrosion cracking of the fuel cladding. Mechanical interaction between the fuel pellets and cladding tube generates a tensile hoop stress. Release of volatile fission products, most likely iodine, provides a corrosive environment. An investigation of stress corrosion crack propagation is performed at 300/degree/C in four Pa flowing iodine environment. By varying the orientation of fracture mechanics specimens, the effect of crystallographic texture, heat treatment, and microstructure on K/sub I/(SCC) is studied. 27 refs.

• Research Organization: MIT, Cambridge, Mass, USA
• OSTI ID: 5333311
• Journal Information: Metall. Trans., A; (United States), Vol. 13A:1
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
REACTOR MATERIALS
STRESS CORROSION
WATER COOLED REACTORS
ZIRCALOY
CRACK PROPAGATION
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
IODINE
MICROSTRUCTURE
ALLOYS
CHEMICAL REACTIONS
CORROSION
CRYSTAL STRUCTURE
ELEMENTS
HALOGENS
MATERIALS
NONMETALS
REACTOR COMPONENTS
REACTORS
TIN ALLOYS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220300* - Nuclear Reactor Technology- Fuel Elements
360105 - Metals & Alloys- Corrosion & Erosion