Heat Treatment of Irradiated Graphite in an Oxidizing Atmosphere


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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.

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E. Bespala

Pilot and Demonstration Center for Decommissioning of Uranium–Graphite Nuclear Reactors

编辑信件的主要联系方式.
Email: bespala_evgeny@mail.ru
俄罗斯联邦, Seversk, Tomsk oblast, 636000

A. Pavlyuk

Pilot and Demonstration Center for Decommissioning of Uranium–Graphite Nuclear Reactors

Email: bespala_evgeny@mail.ru
俄罗斯联邦, Seversk, Tomsk oblast, 636000

S. Kotlyarevskii

Pilot and Demonstration Center for Decommissioning of Uranium–Graphite Nuclear Reactors

Email: bespala_evgeny@mail.ru
俄罗斯联邦, Seversk, Tomsk oblast, 636000

I. Novoselov

National Research Tomsk Polytechnic University

Email: bespala_evgeny@mail.ru
俄罗斯联邦, Tomsk, 634050

Yu. Bespala

National Research Tomsk Polytechnic University

Email: bespala_evgeny@mail.ru
俄罗斯联邦, Tomsk, 634050

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