Heat Treatment of Irradiated Graphite in an Oxidizing Atmosphere

E. V. Bespala, A. O. Pavlyuk, S. G. Kotlyarevskii, I. Yu Novoselov, Yu R. Bespala

Результат исследований: Материалы для журналаСтатьярецензирование

1 Цитирования (Scopus)

Аннотация

It was demonstrated that thermal treatment and decontamination methods can be used for the processing of irradiated nuclear graphite. Special features of the treatment of the irradiated graphite surface with an oxidizing agent were considered. A mathematical model of the interaction of a gaseous oxidizing agent with irradiated graphite was described with consideration for the release of stored Wigner energy. It was established that the qualitative and quantitative compositions of gaseous reaction products depend on thermal and gas-dynamic process conditions. The mathematical models and calculation algorithms proposed can be used for the process optimization of the heat treatment of irradiated graphite for the selective recovery of a number of radionuclides (mainly, 14C and 36Cl), which are concentrated in a thin near-surface layer of graphite components.

Язык оригиналаАнглийский
Страницы (с-по)328-335
Число страниц8
ЖурналSolid Fuel Chemistry
Том52
Номер выпуска5
DOI
СостояниеОпубликовано - 1 сен 2018

ASJC Scopus subject areas

  • Chemistry(all)
  • Chemical Engineering(all)
  • Fuel Technology

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