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There are shown modeling results of the joint utilization process of tributylphosphate’s spent solutions into hexachlorinebutadiene for uranium and plutonium extraction from nitric acid solution of spent nuclear fuel and its recycling wastes. Utilization process was carried out for widely temperature and mass fraction ranges of air plasma coolant. Also optimal consist of inflammable water-organic compositions and modes for practical application this process in air plasma was determined.

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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.