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A Probabilistic-Micromechanical Methodology for Assessing Zirconium Alloy Cladding Failure

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Abstract

Cladding failure of fuel rods caused by hydride-induced embrittlement is a reliability concern for spent nuclear fuel after extended burnup. Uncertainties in the cladding temperature, cladding stress, oxide layer thickness, and the critical stress value for hydride reorientation preclude an assessment of the cladding failure risk. A set of micromechanical models for treating oxide cracking, blister cracking, delayed hydride cracking, and cladding fracture was developed and incorporated in a computer model. Results obtained from the model calculations indicate that at temperatures below a critical temperature of 318.5 °C [605.3 °F], the time to failure by delayed hydride cracking in Zr-2.5%Nb decreased with increasing cladding temperature. The overall goal of this project is to develop a probabilistic-micromechanical methodology for assessing the probability of hydride-induced failure in Zircaloy cladding and thereby establish performance criteria.

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Authors and Affiliations

  1. Center for Nuclear Waste Regulatory Analyses, San Antonio, 78238, TX, USA

    Y. M. Pan

  2. Southwest Research Institute, San Antonio, 78238, TX, USA

    K. S. Chan & D. S. Riha

Authors
  1. Y. M. Pan
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  2. K. S. Chan
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  3. D. S. Riha
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Pan, Y.M., Chan, K.S. & Riha, D.S. A Probabilistic-Micromechanical Methodology for Assessing Zirconium Alloy Cladding Failure. MRS Online Proceedings Library 985, 203 (2006). https://doi.org/10.1557/PROC-985-0985-NN02-03

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  • DOI: https://doi.org/10.1557/PROC-985-0985-NN02-03

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