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Pyrochemical recycling of the nitride SNF of fast neutron reactors in molten salts as a part of the short-circuited nuclear fuel cycle

Jun 28, 2017, 3:50 PM
20m
Room 4 (Yekaterinburg)

Room 4

Yekaterinburg

ORAL Track 4. Fuel Cycle: Sustainability, Environmental Considerations and Waste Management Issues 4.3 Partitioning and Sustainability

Speaker

Prof. Alexei Potapov (Institute of High Temperature Electrochemistry)

Description

The scientific and technological aspects of the pyrochemical recycling of uranium-plutonium nitride nuclear fuel used in the circuited nuclear fuel cycle on the basis of nuclear power plant with fast neutron reactors were considered (in the framework of "Breakthrough" Project). It was expected that the developed pyrochemical technology allows recycling spent nuclear fuel with high energy release (1 year of cooling) and returning of uranium, plutonium and some minor actinides into a reactor. A special attention was paid to the initial process stages, including the nitride SNF component dissolution and ionization of actinide and lanthanide nitrides using the method of “soft chlorination” by transition metal salts. The conditions to prevent uranium and plutonium nitride chloride formation were determined, and they were checked and proved by the laboratory and industrial tests. The corrosion studies of the constructional chromium-nickel alloys in chloride electrolytes containing uranium and lanthanides salts were performed. The studies revealed that the alloys are suitable for production of electrolytic cells and other supporting apparatus operating with molten salts. The complex investigation of physicochemical and electrochemical properties of salt compositions imitating practicable electrolytes for SNF recycling as well as actinide and lanthanide separation with the acceptable separation factor was carried out. The conclusion was drawn on the technological feasibility of the pyrochemical technology realization in a closed nuclear fuel cycle on the basis of nuclear power plant with fast neutron reactors using mixed uranium-plutonium nitride nuclear fuel.

Country/Int. Organization

Russia / Institute of High Temperature Electrochemistry

Primary author

Prof. Alexei Potapov (Institute of High Temperature Electrochemistry)

Co-authors

Dr Alexander Zhidkov (Siberian Chemical Combine, Seversk) Mr Maksim Gerasimenko (Siberian Chemical Combine, Seversk) Mr Sergei Terent’ev (Siberian Chemical Combine, Seversk) Dr Vadim Kovrov (Institute of High Temperature Electrochemistry) Prof. Vladimir Khokhlov (Institute of High Temperature Electrochemistry) Dr Vladimir Shishkin (Institute of High Temperature Electrochemistry) Mr Yuriy Mochalov (Innovation and Technology Center of Project "Breakthrough", Moscow) Prof. Yuriy Zaykov (Innovation and Technology Center of Project "Breakthrough", Moscow)

Presentation materials