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Galvanochemical Technology for Liquid Radioactive Waste Treatment

#2318


Development of Galvanochemical Technology of Liquid Radioactive Waste Treatment with Following Immobilization of Radionuclides in Aluminosilicate Glass Ceramics and Glasses

Tech Area / Field

  • ENV-RWT/Radioactive Waste Treatment/Environment
  • CHE-IND/Industrial Chemistry and Chemical Process Engineering/Chemistry

Status
3 Approved without Funding

Registration date
26.09.2001

Leading Institute
Novosibirsky "VNIPIET", Russia, Novosibirsk reg., Novosibirsk

Supporting institutes

  • Boreskov Institute of Catalysis, Russia, Novosibirsk reg., Akademgorodok\nInstitute of Geology and Mineralogy, Russia, Novosibirsk reg., Novosibirsk\nMining and Chemical Complex, Russia, Krasnoyarsk reg., Zheleznogorsk

Collaborators

  • Sandia National Laboratories, USA, NM, Albuquerque\nNetherlands Energy Research Foundation, The Netherlands, Petten\nLawrence Livermore National Laboratory, USA, CA, Livermore

Project summary

The objective of this project is development of a new technology for purification of liquid radioactive wastes (LRW) containing uranium, neptunium, plutonium, americium and products of their decay, formed at nuclear material processing plants. The technology is based on galvanochemical treatment of wastes, followed by transition of radionuclides to a compact solid phase suitable for further processing and disposal in the form of glass-ceramics and aluminosilicate glasses. The final result of the work will be creation of a conceptual design of a process for liquid radioactive waste treatment intended for use at Russian nuclear material processing enterprises.

The organizations participating in the project are Novosibirsk State Design-Exploratory Institute VNIPIET (NGPII VNIPIET), Institute of Geology of the Siberian Branch of RAS (IG), Boreskov Institute of Catalysis of Siberian Branch of RAS (BIC) and Mining Chemical Complex (MCC) at former Krasnoyarsk-26.

MCC will make inventory of liquid radioactive wastes, study their composition and properties and prepare simulated wastes for the study and optimization of the galvanochemical process in pilot setups at NGPII VNIPIET and BIC. These studies will provide new data on the purification of liquid wastes from heavy metals analogous to actinides and on the effect on the process of various physical fields: magnetic field, vibrofield, etc.

Institute of Geology will study the local base of natural materials with regard to their suitability for preparation of easily caking vitrescent mixtures with iron hydroxide, select compositions of the mixtures based on modified clay materials, determine regimes of drying and shrinkage without breaking material continuity under thermal treatment and perform experimental study of their caking and fusion.

Boreskov Institute of Catalysis will study the composition, structural-mechanical, physical and chemical properties of these materials and mechanism of their transformation upon thermal treatment using a complex of instrumental methods.

The process study under optimum model conditions will be transferred to real conditions at MCC research laboratory, where extensive data on the application of the method proposed to real radioactive wastes and on the long term chemical durability and resistance to radiation of the glasses and glassceramic final forms will be obtained.

Basing on these results NGPII VNIPIET, Institute of Geology, Boreskov Institute of Catalysis and MCC will prepare the conceptual design of the process for purification of liquid radioactive wastes, intended for use at Russian nuclear material processing enterprises. Scientific and technical results obtained during project activities will be also useful to foreign scientists – specialists in liquid radioactive waste treatment.

The collaborative program thus proposed would allow a number of weapons scientists, engineers and technicians in Russia to redirect their talents to the solution of international environmental problems and to solve the particular problem of treating liquid radioactive wastes accumulated at nuclear material processing plants.


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