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Molten Salt Fluoride Fuel


Study of Physico-chemical and Electrochemical Properties of the ADTT Fluoride Nuclear Fuel and Foundation of its Reprocessing

Tech Area / Field

  • FIR-FUE/Reactor Fuels and Fuel Engineering/Fission Reactors

3 Approved without Funding

Registration date

Leading Institute
NIIAR (Atomic Reactors), Russia, Ulianovsk reg., Dimitrovgrad

Project summary

The results of work may be employed for experimental development of the closed fuel cycle of the ADTT nuclear power plant operating in the mode of radioactive waste burning and using molten salt fluoride fuel. The project tasks are as follows:
1. Experimental study of physical-chemical and electrochemical properties of nuclear fluoride fuel with plutonium and minor-actinides. (Determination of the limits to actinide fluoride solubility in fuel and its redox potential).
2. Experimental evaluation of plutonium and minor-actinide behavior during reprocessing of the system "molten fuel-liquid alloy".

Expected Results

1. Experimental data on plutonium and minor-actinide fluoride solubility in the ternary mixtures of lithium, beryllium and zirconium fluorides.
2. Experimental data on electrochemical behavior of plutonium redox potential in fluoride melts during pyroelectrochemical reprocessing of molten salt fuel.
3. Experimental data on the separation factors of plutonium and fission products during electrochemical reprocessing.
4. Generalized calculation data on the standard potentials of lanthanides and actinides in fluoride melts.

Potential Participation of Foreign Partners

Discussion of the results, cooperative work in planning of the project.


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