Институт физической химии и электрохимии имени А. Н. Фрумкина РАН, Москва 3 Институт проблем безопасного развития атомной энергетики РАН, Москва 4 АО «Опытно-демонстрационный центр вывода из эксплуатации уран-графитовых ядерных реакторов», г. Северск Статья поступила в редакцию 7 мая 2019 г Рассмотрено состо ние работ и исследовани по обра ени с облу енным реакторным ра итом редло ены варианты оптими а ии расходов на ахоронение Р вкл а ра работку и применение методов де актива ии сни ени активности ра итовых Р сни ени стоимости про едур конди ионировани Р а так е со дание спе иали ированно о пункта ахоронени Р писаны основные пути дл достиени про ресса и уто нени плана исследовани и ра работок в асти удалени ра ита на ахоронение Ключевые слова: радиоактивные отходы радиоу лерод реакторны ра ит уран ра итовы реактор ахоронение Р пункт ахоронени Р
The paper presents the results of the best material selection for additional safety barrier construction during uranium-graphite reactors decommissioning. The research findings show that the best material for safety barriers is clay-containing natural material of various types with counter-migrational and counter-filtrational qualities. We have demonstrated a technology for void-free filling of cavities in the reactor space of under-decommissioning uranium-graphite reactors on the site of JSC Pilot and Demonstration Center for Decommissioning of Uranium-Graphite Nuclear Reactors (PDC UGR). This will make it possible to construct reliable man-made geo-barriers and prevent the release of radionuclides from the repository into the environment for thousands of years.
The paper discusses engineering, economic and legislative aspects influencing the ways of addressing the problem associated with the final stage of irradiated graphite management from water-graphite NPP reactor units in Russia. It presents some calculated and experimental data demonstrating the feasibility of introducing some corrective changes to the legislative and regulatory framework existing in the Russian Federation to enable near-surface disposal of irradiated graphite from power reactors.
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