ТЕХНОЛОГИИ ОБРАЩЕНИЯ С НАТРИЕМ ПРИ ВЫВОДЕ ИЗ ЭКСПЛУАТАЦИИ РЕАКТОРА НА БЫСТРЫХ НЕЙТРОНАХ: ОБЗОР

Реакторы на быстрых нейтронах с натриевым теплоносителем в настоящее время демонстрируют наибольшую технологическую готовность к промышленной эксплуатации и переходу к замкнутому ядерному топливному циклу. В то же время расширение парка атомных станций с быстрыми натриевыми реакторами в перспективе неизбежно приведёт к необходимости решения задач их вывода из эксплуатации. Одной из ключевых проблем данного этапа является использование натрия в качестве теплоносителя, что обусловлено его физико-химическими свойствами. Эти физико-химические особенности существенно усложняют процессы демонтажа и дезактивации оборудования реакторных установок. В связи с этим особую ценность представляет накопленный опыт обращения с натрием при выводе из эксплуатации опытно-демонстрационных быстрых натриевых реакторов. Таким образом, в настоящей статье представлен обзор современных и перспективных технологий обращения с натрием на этапе вывода из эксплуатации реакторов на быстрых нейтронах.

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