Observations on damage accumulation during iodine-induced stress corrosion cracking of Zircaloy cladding. [PWR; BWR]

Journal Article · Thu Mar 01 04:00:00 EST 1979 · Nucl. Technol.; (United States)

OSTI ID:6447274

Jones, R L ^[1]; Smith, E; Miller, A K

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1. Electric Power Research Inst., Palo Alto, CA

A predictive model has recently been proposed for pellet-cladding interaction (PCI) failures of water reactor fuel rods. The model is based on the assumption that PCI failures are attributable to stress corrosion cracking (SCC) of the Zircaloy cladding induced by fission product iodine. Because the kinetics of iodine-induced SCC of irradiated Zircaloys are not well-documented at present, the PCI model is based largely on failure-time data from constant stress tube pressurization experiments.

• OSTI ID: 6447274
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 42:3; ISSN NUTYB
• Country of Publication: United States
• Language: English

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