1. G. P. Kobylyanskii, V. K. Shamardin, and A. Ya. Rogozyanov, “Features of the influence of reactor irradiation on the properties and behavior of zirconium alloys,” in Proc. of 6 Russian Conf. on Reactor Materials Science, 11–15 September 2000 (NIIAR, Dimitrovgrad, 2001) Vol. 1, pp. 303–322 (2001).
2. D. Olander and A. Motta, Light Water Reactor Materials, Volume I: Fundamentals (American Nuclear Society, 2017).
3. J. J. Kearns and C. R. Woods, “Effect of texture, grain size and cold work on the precipitation of oriented hydrides in Zircaloy tubing and plate,” J. Nucl. Mater. 20, 241–261 (1966).
4. G. L. Garner and J. P. Mardon, “Performance of alloy M5 in a high duty U.S. reactor,” Nucl. Eng. Int. (2002). https://www.mne.psu.edu/motta/.
5. R. Murgatroyd and A. Rogerson, “An assessment of the influence of microstructure and test conditions on the irradiation growth phenomenon in zirconium alloys,” J. Nucl. Mater. 90, 240–248 (1980).