1. Ambartsumyan, R., Kiselev, A., et al., 1959. Mechanical properties and corrosion resistance of zirconium and its alloys in water, steam and gases at elevated temperatures. Tech. rep., USSR/A/CONF.15/P/2044.
2. Ang, C., Raiman, S., Burns, J., Hu, X., Katoh, Y., 2017. Evaluation of the First Generation Dual-purpose Coatings for SiC Cladding. Tech. rep., ORNL, SR-2018/318.
3. CANDU-6 Technical Summary;Atomic Energy of Canada Limited,2005
4. The Moderator Liquid Poison System;Bieman,1992
5. Brachet, J., Le Saux, M., Le Flem, M., Urvoy, S., Rouesne, E., Guilbert, T., Cobac, C., Lahogue, F., Rousselot, J., Tupin, M., et al., 2015. On-going studies at CEA on chromium coated zirconium based nuclear fuel claddings for enhanced accident tolerant LWRs fuel. In: Top Fuel 2015, September 13–17. Zurich, Switzerland, pp. 13–19.