Evaluation of missing pellet surface geometry on cladding stress distribution and magnitude

Nathan Capps, Robert Montgomery, Dion Sunderland, Martin Pytel, Brian D. Wirth

Research output: Contribution to journalArticlepeer-review

14 Scopus citations

Abstract

Missing pellet surface (MPS) defects are local geometric defects in nuclear fuel pellets that result from pellet mishandling or manufacturing. The presence of MPS defects can cause significant clad stress concentrations that can lead to through-wall cladding failure for certain combinations of fuel burnup, and reactor power level or power change. Consequently, the impact of MPS defects has limited the rate of power increase, or ramp rate, in both pressurized and boiling water reactors (PWRs and BWRs, respectively). Improved three-dimensional (3-D) fuel performance models of MPS defect geometry can provide better understanding of the probability for pellet clad mechanical interaction (PCMI), and correspondingly the available margin against cladding failure by stress corrosion cracking (SCC). The Consortium of Advanced Simulations of Light Water Reactors (CASL) has been developing the Bison-CASL fuel performance code to consider the inherently multi-physics and multi-dimensional mechanisms that control fuel behavior, including cladding stress concentrations resulting from MPS defects. This paper evaluates the cladding hoop stress distributions as a function of MPS defect geometry with discrete pellet radial cracks for a set of typical operating conditions in a PWR fuel rod. The results provide a first step toward a probabilistic approach to assess cladding failure during power maneuvers. This analysis provides insight into how varying pellet defect geometries affect the distribution of the cladding stress, as well as the temperature distributions within the fuel and clad; and are used to develop stress concentration factors for comparing 2-D and 3-D models.

Original languageEnglish
Pages (from-to)51-63
Number of pages13
JournalNuclear Engineering and Design
Volume305
DOIs
StatePublished - Aug 15 2016
Externally publishedYes

Funding

This research was supported by the Consortium for Advanced Simulation of Light Water Reactors ( http://www.casl.gov ), an Energy Innovation Hub ( http://www.energy.gov/hubs ) for Modeling and Simulation of Nuclear Reactors under U.S. Department of Energy Contract No. DE-AC05-00OR2272.

FundersFunder number
Consortium for Advanced Simulation of Light Water Reactors
Energy Innovation Hub
Modeling and Simulation of Nuclear Reactors
U.S. Department of Energy

    Keywords

    • JEL classification E. Fuel engineering

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