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Investigation of High-temperature Oxidation Kinetics and Residual Ductility of Oxidized Samples of Sponge-based E110 Alloy Cladding Tubes

Published online by Cambridge University Press:  20 December 2016

Y. Yan*
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
B. E. Garrison
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
T. S. Smith
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
M. Howell
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
J. R. Keiser
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
G. L. Bell
Affiliation:
Oak Ridge National Laboratory, Oak Ridge, TN 37831, U.S.A.
*
*(Email: yy9@ornl.gov)
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Abstract

Two-sided oxidation experiments were recently conducted at 1000-1200°C in flowing steam with samples of sponge-based Zr-1Nb alloy E110. Although the old electrolytic E110 tubing exhibited a high degree of susceptibility to nodular corrosion and experienced breakaway oxidation rates in relatively short time, the new sponge-based E110 has demonstrated steam oxidation behavior comparable to Zircaloy-4. The sponge-based E110 followed the parabolic law, and the derived oxidation rate constant is in good agreement with the Cathcart-Pawel (CP) correlation at 1100-1200°C. For 1000°C oxidation, the weight-gain of sponge-based E110 is much lower than Zircaloy-4. No breakaway oxidation was observed at 1000°C up to 8000 s. Ring compression tests were conducted to evaluate the residual ductility of oxidized samples at room temperature and at 135°C. All sponge-based E110 specimens were still ductile at 135°C after being oxidized up to 20% equivalent cladding reacted at 1000-1200°C. Metallographic examinations were performed on oxidized E110 specimens to correlate material performance with microstructure.

Type
Articles
Copyright
Copyright © Materials Research Society 2016 

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References

REFERENCES

Cathcart, J. V., Pawel, R. E., McKee, R. A., Druschel, R. E., Yurek, G. J., Cambell, J. J., and Jury, S. H., “Zirconium Metal-Water Oxidation Kinetics: IV. Reaction Rate Studies,” ORNL/NUREG-17, Aug. 1977.Google Scholar
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).Google 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
Yan, Y., Burtseva, T., and Billone, M., “High Temperature Oxidation Behavior of Zr-1Nb Cladding Alloy E110,” J. Nucl. Mater. 393, 433448 (2009).Google Scholar
Garde, A. M., Comstok, R. J., Pan, G., Baranwal, R., Hallstadius, L., Cook, T., and Carrera, F., “Advanced Zirconium Alloy for PWR Application,” J. ASTM Intl., Vol. 7, No. 9 doi:10.1520/JAI103030.Google Scholar
Chabretou, V., Hoffmann, P. B., Trapp-Pritsching, S., Garner, G., Barberis, P., Rebeyrolle, V. and Vermoyal, J. J., “Ultra Low Tin Quaternary Alloys PWR Performance-Impact of Tin Content on Corrosion Resistance, Irradiation Growth, and Mechanical Properties,” J. ASTM Intl., Vol. 8, No. 5, doi:10.1520/JAI103013.Google Scholar
Yegorova, L., Lioutov, K., Jouravkova, N., Konobeev, A., Smirnov, V., Chesanov, V., and Goryachev, A., “Experimental Study of Embrittlement of Zr-1%Nb VVER Cladding under LOCA-Relevant Conditions,” NUREG/IA-0211, March 2005.Google Scholar
Mardon, J. P., Brachet, J. C., Portier, L., Maillot, V., Forgeron, T., Lesbros, A., and Waeckel, N., “Influence of Hydrogen Simulating Burn-Up Effects on the Metallurgical and Thermal-Mechanical Behavior of M5™ and Zircaloy-4 Alloys under LOCA Conditions,” ICONE13-50457, 13th Intl. Conf. on Nucl. Eng., Beijing, China, May 16-20, 2005, p. 19.Google Scholar