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Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions

Daum, RS
Engineer,Argonne National Laboratory,IL,

Majumda, S
Senior Engineer,Argonne National Laboratory,IL,

Tsai, H
Engineer,Argonne National Laboratory,IL,

Bray, TS
Engineer,Argonne National Laboratory,IL,

Koss, DA
Professor,The Pennsylvania State University,PA,

Motta, AT
Associate Professor,The Pennsylvania State University,PA,

Billone, MC
Program Manager and Engineer,Argonne National Laboratory,IL,


Pages: 16    Published: Jan 2002


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Source: STP1418-EB


Abstract

Specimen geometries have been developed to determine the mechanical properties of irradiated Zircaloy cladding subjected to the mechanical conditions and temperatures associated with reactivity-initiated accidents (RIA) and loss-of-coolant accidents (LOCA). Miniature ring-stretch specimens were designed to induce both uniaxial and plane-strain states of stress in the transverse (hoop) direction of the cladding. Also, longitudinal tube specimens were also designed to determine the constitutive properties in the axial direction. Finite-element analysis (FEA) and experimental parameters and results were closely coupled to optimize an accurate determination of the stress-strain response and to induce fracture behavior representative of accident conditions. To determine the constitutive properties, a procedure was utilized to transform measured values of load and displacement to a stress-strain response under complex loading states. Additionally, methods have been developed to measure true plastic strains in the gauge section and the initiation of failure using real-time data analysis software. Strain rates and heating conditions have been selected based on their relevance to the mechanical response and temperatures of the cladding during the accidents.


Keywords:
mechanical properties, Zircaloy cladding, ring stretch specimens, axial specimens

Paper ID: STP10821S
Committee/Subcommittee: E10.02
DOI: 10.1520/STP10821S
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