Abstract

The article focuses on discussion of problem of graphite radioactive waste formation and accumulation. It is shown that irradiated nuclear graphite being inalienable part of uranium-graphite reactor may contain fission and activation products. Much attention is given to the process of formation of radioactive cesium on the graphite element surface. It is described a process of plasma decontamination of irradiated graphite in inert argon atmosphere. Quasi-one mathematical model is offered, it describes heat transfer process in graphite-cesium-argon system. Article shows results of calculation of temperature field inside the unit cell. Authors determined the factors which influence on temperature change.

Highlights

  • All of the industrial uranium-graphite reactors (IUGR) are stopped in Russia

  • Exception is IUGR EI-2, which was replaced on special radioactive waste parking site

  • It is necessary to conduct operations connected with graphite stack disassembling and further radioactive waste burial for reactors of types of RBMK, EGP, AMB, AM reactors of types of Magnox, UNGG, AGR, HTR

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Summary

Introduction

All of the industrial uranium-graphite reactors (IUGR) are stopped in Russia. Upon that major part of them is either on the stage of shut down preparation or on the stage of shut down. One of the most common radionuclides present in irradiated structural elements is 137Cs. the specific activity of the nuclide in some samples of radiation sources can reach 3.2 TBq/kg [1]. The specific activity of the nuclide in some samples of radiation sources can reach 3.2 TBq/kg [1] In this case the radioactive cesium contamination observed in the materials that were in contact with nuclear fuel, since it is the product nuclear fission. At the same time there is a transition from surface to volume processes This is especially true during deactivation of graphite structural elements, the porosity of which is about 23 % [8]. Simulations of heat transfer process in a high temperature argon flow for selecting of optimal regimes of graphite cleaning process by 137Cs

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