1. S. V. Alekseev and V. A. Zaitsev, Nitride Fuel for Nuclear Power, Technosphere, Moscow (2013).
2. State-of-the-Art Report on Innovative Fuels for Advanced Nuclear Systems, NEA Rep. No. 6895 (2014).
3. R. B. Kotel’nikov, S. N. Bashlykov, A. I. Kashtanov, and T. S. Men’shikova, High-Temperature Nuclear Fuel, Atomizdat, Moscow (1978).
4. S. Mishra, S. Kaity, J. Banerjee, et al., “U–PuO2, U–PuC, U–PuN cermet fuel for fast reactor,” J. Nucl. Mater., 499, 272–283 (2018).
5. K. N. Dvoeglazov, A. N. Shadrin, O. V. Shchudegova, et al., “Oxidation of model uranium-plutonium nitride fuel and the effect of this process on dissolution in nitric acid,” Vopr. At. Nauki Tekhn., No. 4 (87), 81–90 (2016).