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Modeling of Radioactive Graphite Oxidation in Molten Salts: Computer Experiment

Published online by Cambridge University Press:  15 February 2011

Nikolai M. Barbin ,
Dmitri I. Terentiev ,
Sergei G. Alekseyev ,
Marat A. Tuktarov  and
A. A. Romenkov
Nikolai M. Barbin
Affiliation:
Ural Institute of State Fire Fighting Service, 22 Mira St., Ekaterinburg, 620062Russia Institute of High-Temperature Electrochemistry, Ural Branch RAS, Ekaterinburg, Russia
Dmitri I. Terentiev
Affiliation:
Ural Institute of State Fire Fighting Service, 22 Mira St., Ekaterinburg, 620062Russia
Sergei G. Alekseyev
Affiliation:
Ural Institute of State Fire Fighting Service, 22 Mira St., Ekaterinburg, 620062Russia
Marat A. Tuktarov
Affiliation:
N.A. Dolezhal R&D Institute of Power Engineering, Moscow, Russia
A. A. Romenkov
Affiliation:
N.A. Dolezhal R&D Institute of Power Engineering, Moscow, Russia
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Abstract

Graphite is used as the neutron moderator and reflector in many nuclear reactors. Obsolete graphite nuclear reactors are put out of operation, leading to formation of a large quantity of radioactive graphite waste.

It is proposed that irradiated reactor graphite is processed by high-temperature chemical oxidation in salt melts with an oxidant, which is part of the salt melt, leading to formation of exhaust gases: gaseous compounds of carbon and oxygen (CO2 and CO).

This study deals with carbon oxidation and physical-chemical transformations of radioactive elements during the interaction between graphite waste of the atomic power industry and salt melts. The method of thermodynamic simulation is used. The carbon melt decreases the transfer of radionuclides to the gaseous phase as compared to incineration of graphite in the atmosphere.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 1193: Scientific Basis for Nuclear Waste Management XXXIII , 2009 , 359
Copyright
Copyright © Materials Research Society 2009

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References

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