Aref’yev, K., Vorontsova, L., Zablotskaya, T., et al. (1974). Diffusion coefficients of alkali metal vapors in inert gases.
Auciello, O., Gras-Mart´ı, A., Valles-Abarca, J. A., et al. (2012). Plasma-surface interactions and processing of materials, volume 176. Springer Science & Business Media.
Barbin, N., Shavaleev, M., Terentyev, D., et al. (2015). Computer simulation of thermodynamic processes with involvement of actinoids heating radioactive graphite in the nitrogen atmosphere. Applied Physics, 6:42–7.
Bespala, E., Myshkin, V., Pavlyuk, A., et al. (2017). Heat and mass transfer in cesium evaporation from graphite surface in argon. Atomic Energy, 122(6):400–405.
Bespala, E., Novoselov, I., and Ushakov, I. (2016). Heat transfer during evaporation of cesium from graphite surface in an argon environment. In MATEC Web of Conferences, volume 72, page 01011. EDP Sciences.
Bespala, E., Novoselov, I. Y., Pavlyuk, A., et al. (2018). Study of evaporating the irradiated graphite in equilibrium low-temperature plasma. Thermophysics and Aeromechanics, 25(1):109–117.
Bespala, E., Pavliuk, A., Kotlyarevskiy, S., et al. (2019). Modeling of processing of irradiated graphite contained fission and neutron-activation products by noble gas flow. In AIP Conference Proceedings, volume 2101, page 020004. AIP Publishing LLC.
Bushuev, A., Aleeva, T., Petrova, E., et al. (2003). Possibility of salvaging spent graphite sleeves from the reactors of the siberian chemical combine by incineration. Atomic Energy, 94(2):91–98.
Bushuev, A., Kozhin, A., Zubarev, V., et al. (2015). Radioactive contamination of spent reactor graphite. Atomic Energy, 117(3):196–200.
Dunzik-Gougar, M. L. and Smith, T. E. (2014). Removal of carbon-14 from irradiated graphite. Journal of Nuclear Materials, 451(1-3):328–335.
Fachinger, J., von Lensa, W., and Podruhzina, T. (2008). Decontamination of nuclear graphite. Nuclear Engineering and Design, 238(11):3086–3091.
IAEA (2001). Methods for the minimization of radioactive waste from decontamination and decommissioning of nuclear facilities. Technical report, Vienna, Austria.
IAEA (2008). Innovative and adaptive technologies in decommissioning of nuclear facilities: Final report of a coordinated research project 2004-2008. Technical report, Vienna, Austria.
Kane, J. J., Karthik, C., Ubic, R., et al. (2013). An oxygen transfer model for high purity graphite oxidation. Carbon, 59:49–64.
Kuijper, J., Raepsaet, X., De Haas, J., et al. (2006). HTGR reactor physics and fuel cycle studies. Nuclear Engineering and Design, 236(5-6):615–634.
Laraia, M. (2012). Nuclear decommissioning. Planning, Execution and International.
Pavliuk, A., Zagumennov, V., Kotlyarevskiy, S., et al. (2018a). Thermodynamic simulation of equilibrium composition of reaction products at dehydration of a technological channel in a uranium-graphite reactor. Thermal Engineering, 65(1):51–56.
Pavliuk, A. O., Kotlyarevskiy, S. G., Bespala, E. V., et al. (2018b). Experience of on-site disposal of production uranium-graphite nuclear reactor. Journal of Environmental Radioactivity, 184:22–31.
Sato, H. and Yan, X. L. (2019). Study of an HTGR and renewable energy hybrid system for grid stability. Nuclear Engineering and Design, 343:178–186.
Theodosiou, A., Jones, A., Burton, D., et al. (2018). The complete oxidation of nuclear graphite waste via thermal treatment: An alternative to geological disposal. Journal of Nuclear Materials, 507:208–217. Vulpius, D., Baginski, K., Kraus, B., et al. (2013). Thermal treatment of neutron-irradiated nuclear graphite. Nuclear Engineering and Design, 265:294–309.
Wickham, A., Steinmetz, H.-J., O’Sullivan, P., et al. (2017). Updating irradiated graphite disposal: Project ‘GRAPA’ and the international decommissioning network. Journal of Environmental Radioactivity, 171:34–40.
Young, D. A. (1975). Phase diagrams of the elements. Technical report, California Univ.
