Abstract
Understanding the precipitation of brittle hydride phases is crucial in establishing a failure criterion for various zirconium alloy nuclear fuel cladding. Accordingly, it is important to quantify the sensitivity of hydride precipitation to the component microstructure. This experimental investigation focuses on two microstructural characteristics and their role as hydride nucleation sites: The grain size and the alloy chemical composition. Samples of commercially pure zirconium (Zr-702) and Zircaloy-4, each with a wide range of grain sizes, were hydrided to 100 ppm and micrographs of the hydride distribution were optically analyzed for inter-granular and intra-granular precipitate sites. For most grain sizes, it was found that a significantly lower fraction of the precipitated hydrides nucleated at grain boundaries in Zircaloy-4 than in Zr-702, suggesting that a higher SPP content encourages the formation of intra-granular hydrides. Moreover, this effect became more prominent as the grain size increased; large-grain specimens contained a higher fraction of intra-granular hydrides than small-grain specimens of both Zr-702 and Zircaloy-4, highlighting the potency of grain boundaries as nucleation sites and how SPPs can influence the hydride distribution profile.
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References
M.P. Puls, The Effect of Hydrogen and Hydrides on the Integrity of Zirconium Alloy Components: Delayed Hydride Cracking, 1st ed. (Springer, London, 2012) p. 7–336.
D. Northwood, Mater. Des. 6 (2) 58–56 (1985).
J. Gros and J. Wadier, J. Nucl. Mater. 172 (1) 85–96 (1990).
Kearns, J. Nucl. Mater. 22 (3) 292–303 (1967).
M. Patel, S. Waheed, M.R. Wenman, A.P. Sutton and D.S. Balint, MRS Advances 2 (55) 3353–3358 (2017).
S. Shi, G. Shek and M.P. Puls, J. Nucl. Mater. 218 (2) 189–201 (1995).
ASTM International in Standard Test Method for Determination of Hydrogen in Titanium and Titanium Alloys by Inert Gas Fusion Thermal Conductivity/Infrared Detection Method (ASTM E1447, 2009).
V. Tong and T. Britton. Acta Mater. 129 510–520 (2017).
L. Bramwell, J. Haste, D. Worswick and D. Parsons in An Experimental Investigation into the Oxidation of Zircaloy-4 at Elevated Pressures in the 750 to 1000ºC Temperature Range (Zirconium in the Nuclear Industry: Tenth International Symposium, ASTM STP 1245, 1994).
H. Weekes, N. Jones, T. Lindley and D. Dye, J. Nucl. Mater. 478 32–41 (2016).
D. Westlake, J. Nucl. Mater. 16 215–219 (1965).
C. Ells, J. Nucl. Mater. 28 (2) 129–151 (1968).
J.W. Christian, The Theory of Transformations in Metals and Alloys, 3rd ed. (Pergamon, Amsterdam, 2002) p. 356.
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El Chamaa, S., Patel, M., Davies, C.M. et al. The Effect of Grain Boundaries and Second-Phase Particles on Hydride Precipitation in Zirconium Alloys. MRS Advances 3, 1749–1754 (2018). https://doi.org/10.1557/adv.2018.111
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DOI: https://doi.org/10.1557/adv.2018.111