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Author Park, Sang Yoon ♦ Kim, Jun Hwan ♦ Choi, Byung Kwon ♦ Jeong, Yong Hwan
Source SpringerLink
Content type Text
Publisher The Korean Institute of Metals and Materials
File Format PDF
Copyright Year ©2007
Language English
Subject Domain (in DDC) Technology ♦ Engineering & allied operations
Subject Keyword nuclear fuel cladding ♦ iodine-induced stress corrosion cracking ♦ crack initiation ♦ zirconium ♦ pitting nucleation ♦ K$_{ISCC}$ ♦ Metallic Materials ♦ Operating Procedures, Materials Treatment ♦ Magnetism, Magnetic Materials ♦ Engineering Thermodynamics, Heat and Mass Transfer ♦ Characterization and Evaluation of Materials ♦ Continuum Mechanics and Mechanics of Materials
Abstract Tests of iodine-induced stress corrosion cracking (ISCC) were carried out to elucidate the initiation and propagation of cracks in the claddings of zirconium alloys. Zircaloy-4 cladding and Nb-contained zirconium cladding were pressurized with and without a pre-cracked state at 350°C in an iodine environment. The results show that pitting nucleation and growth play an important role in initiating ISCC. Pits preferentially grow and agglomerate around the grain boundary, where the number of pits increases with the iodine concentration and the hoop stress of the claddings. A model of grain-boundary pitting coalescence and a model of pitting-assisted slip cleavage, which were proposed to clearly elucidate the crack initiation and propagation process under ISCC, produce reasonable results. The Nb-contained zirconium cladding exhibits higher ISCC resistance than Zircaloy-4 from the standpoint of a higher threshold stress-intensity factor and a lower crack propagation rate.
ISSN 15989623
Age Range 18 to 22 years ♦ above 22 year
Educational Use Research
Education Level UG and PG
Learning Resource Type Article
Publisher Date 2007-01-01
Publisher Place Seoul
e-ISSN 12344320
Journal Metals and Materials
Volume Number 13
Issue Number 2
Page Count 9
Starting Page 155
Ending Page 163


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Source: SpringerLink