Method for purifying circulating melt of fluoride salts in a liquid-salt reactor

Abstract

The utility model relates to the field of nuclear energy and is intended for the purification of circulating fluoride salt melts in molten salt reactor installations, including those implementing the thorium fuel cycle. The method includes taking a portion of the circulating melt from the main circulation circuit of the reactor, directing said portion of the melt through a bypass line into a sorption-filtration module, passing the melt through a filter layer and returning the purified melt back to the circulation circuit. Filtration is carried out through a sorption-filtration material based on modified diatomite with a porosity of 60–85% and a pore size of 5–200 µm, formed as granules, porous blocks, or multilayer filtration cassettes. The technical result consists of increasing the purification efficiency of the circulating fluoride salt melt due to the simultaneous mechanical retention of solid particles and the sorption binding of colloidal impurities. The utility model was developed within the framework of the implementation of the scientific and technical program IRN BR24993225 for program-targeted financing of the Science Committee of the Ministry of Science and Higher Education of the Republic of Kazakhstan for 2024–2026.