Method for separating nuclear fuel material from ionic liquid extraction system

Abstract

The invention provides a method for reseperating nuclear fuel from the ironic liquid extraction system for load nuclear fuel, which strips nuclear fuel from ironic liquid extraction system by stripping agent carbonate solution. The reaction condition of the method is simple and mild, and the extraction system maintains its extraction function after multiple extraction-stripping cycles. The stripping agent includes sodium carbonate, potassium carbonate, lithium carbonate and other inorganic carbonates, guanidine carbonate and derivatives thereof, hydrazine carbonate and derivatives thereof and quaternary ammonium carbonate, the carbonates are easily available in market. The organic acid salt has more advantage in post treatment, can be completely eliminated by roasting of the stripping agent containing organic acid salt, without leaving ash, which is beneficial to the next treatment of nuclear fuel.

Description

technical field [0001] The invention relates to nuclear industry post-processing technology, in particular to a method for nuclear fuel extraction system. Background technique [0002] The application of nuclear fuel is an important way to solve the world's energy security. At present, the utilization rate of uranium resources in thermal reactor nuclear power plants operating in the world is less than 1%. According to the proven uranium resources and uranium fuel utilization levels on the earth, China's uranium reserves can only be used for 60-70 years. Therefore, improving the utilization rate of uranium resources and minimizing nuclear waste is the key to nuclear energy utilization and sustainable development. The key technology is the fast neutron reactor nuclear energy system and its corresponding nuclear fuel closed cycle system. Some people estimate that if fast reactors and nuclear fuel closed cycle technology are adopted, the uranium resources on the earth can be us...

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