Zirconium in the Nuclear Industry 1979
DOI: 10.1520/stp36670s
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Zircaloy Performance in Light-Water Reactors

Abstract: The Zircaloys-2 and -4 are the principal metallic components of light-water reactor (LWR) fuel assemblies. This paper reviews progress in our understanding of Zircaloy behavior in the LWR environment. A significant body of data has been obtained on the characteristics of stress corrosion cracking pellet-cladding interaction (PCI) failures and on the mechanical stability of both fuel rod and assembly. All indications are that the mechanical performance of Zircaloy components is well understood and that cladding… Show more

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Cited by 5 publications
(3 citation statements)
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“…These differences are most likely related to the approaches used in the stress analysis of fuel pellet cracks, which form the basis for the classical PCI methods used in Falcon and RODEX-4. 3-D Bison-CASL stress concentration factor, as a function of MPS defect width, compared to values from literature [3,14].…”
Section: -D Five Pellet Model With Mps Defectmentioning
confidence: 99%
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“…These differences are most likely related to the approaches used in the stress analysis of fuel pellet cracks, which form the basis for the classical PCI methods used in Falcon and RODEX-4. 3-D Bison-CASL stress concentration factor, as a function of MPS defect width, compared to values from literature [3,14].…”
Section: -D Five Pellet Model With Mps Defectmentioning
confidence: 99%
“…
INTRODUCTIONPellet cladding interaction (PCI) in light water reactor (LWR) fuel is a coupled thermal-chemicalmechanical process that can lead to cladding breach and release of radioactive fission products into the coolant under certain conditions of operating history, power change, and fuel rod design characteristics [1][2][3][4]. Reactor operating restrictions, which limit power maneuvering, have been established to mitigate PCI, but they restrain operational flexibility and lead to loss of power generation.
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confidence: 99%
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