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Ductility Evaluation of As-Hydrided and Hydride Reoriented Zircaloy-4 Cladding under Simulated Dry-Storage Condition

Published online by Cambridge University Press:  25 February 2014

Y. Yan ,
L. K. Plummer ,
H. Ray ,
T. Cook  and
H. Z. Bilheux
Y. Yan
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
L. K. Plummer
Affiliation:
University of Oregon, Eugene, OR 97403, U.S.A.
H. Ray
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
T. Cook
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
H. Z. Bilheux
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
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Abstract

Pre-storage drying-transfer operations and early stage storage expose cladding to higher temperatures and much higher pressure-induced tensile hoop stresses relative to normal operation in-reactor and pool storage under these conditions. Radial hydrides precipitate during cooling and could provide an additional embrittlement mechanism as the cladding temperature decreases below the ductile-to-brittle transition temperature. To simulate this behavior, unirradiated Zircaloy-4 samples were hydrided by a gas charging method to levels that encompass the range of hydrogen concentrations observed in current used fuel. Mechanical testing was carried out by the ring compression test (RCT) method at various temperatures to evaluate the sample’s ductility for both as-hydrided and post-hydride reorientation treated specimens. As-hydrided samples with higher hydrogen concentration (>800 ppm) resulted in lower strain before fracture and reduced maximum load. Increasing RCT temperatures resulted in increased ductility of the as-hydrided cladding. A systematic radial hydride treatment was conducted at various pressures and temperatures for the hydrided samples with H content around 200 ppm. Following the radial hydride treatment, RCTs on the hydride reoriented samples were conducted and exhibited lower ductility compared to as-hydrided samples.

Keywords

ductilityZrH
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1645: Symposium EE/ZZ – Advanced Materials in Extreme Environments , 2014 , mrsf13-1645-ee01-03
Copyright
Copyright © Materials Research Society 2014 

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References

REFERENCES

Billone, M. C., Yan, Y., Burtseva, T., and Daum, R., “Cladding Embrittlement during Postulated Loss-of-Coolant Accidents,” NUREG/CR–6967 ANL-07/04 (2008).CrossRefGoogle Scholar
Yan, Y., Burtseva, T. A., and Billone, M. C., “Post-quench Ductility Results for North Anna Highburnup 17×17 ZIRLO Cladding with Intermediate Hydrogen Content,” ANL letter report to NRC, April 17, 2009.Google Scholar
Billone, M. C., Burtseva, T., and Yan, Y.. “Overview of Spent Nuclear Fuel Program: Test Plan and High Burnup Cladding at ANL,” NRC Program Review Meeting, Argonne National Laboratory, Argonne, IL, July 7, 2010.Google Scholar
Daum, R., Tsai, H., Liu, Y., and Billone, M., “High-Burnup Cladding Mechanical Performance during Cask Storage and Post-Storage Handling and Transportation,” Nuclear Safety Research Conference, Washington, D.C., October 25-27, 2004.Google Scholar
Billone, M. C., Burtseva, T., and Einzuger, R.E., “Dutile-to-Brittle Transition Temperature for High-Burnup Cladding Alloys Exposed to Simulated Drying-Storage Condition,” J. Nucl. Mater. 433, 431 (2013).CrossRefGoogle Scholar
Cuta, J., “Temperature Histories in Typical Dry Storage Conditions,” Review Meeting of Argonne’s High-Burnup SNF Transport Program, Argonne, IL, July 7, 2010.Google Scholar
Yan, Y., Blackwell, A. S., Plummer, L. K., Radhakrishnan, B., Gorti, S. B., and Clarno, K. T., “Observation and Mechanism of Hydride in Zircaloy-4 and Local Radial Hydride Induced by High Pressure at High Temperatures,” 2013 International High-Level Radioactive Waste Management, Albuquerque, NM, April 28 – May 2, 2013.Google Scholar