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Valentin A. Boldakov, Sergey S. Poglyad, Alexander S. Kornilov, Olga S. Dmitrieva, Vladimir N. Momotov, Natalya O. Pozigun, Anastasia A. Telnova
Cesium separation from spent fuel and
molybdenum trioxide joint high temperature treatment product process
modification
Abstract
Abstract. Technological scheme of cesium
extraction from spent nuclear fuel before hydrometallurgical reprocessing is
developing in order to decrease spent fuel heat dissipation and specific
activity. The scheme includes spent fuel and molybdenum trioxide joint high
temperature treatment, cesium removing by alkali solution product flushing and
fuel dissolution in nitric acid. Technology realization will provide spent fuel
cooling time reduction and radiation impact to personnel, furniture and
solutions decrement. Sintering temperature, different flushing solutions
efficiency and cesium fractioning duration researches results are presented in
the article. Researches were providing in laboratory conditions with spent fuel
imitators and radionuclide markers using.
Key words: spent fuel, spent fuel high
temperature treatment, cesium, cesium-137 radioisotope, triuranium octaoxide,
molybdenum trioxide, mixed hexacyanoferrates
Copyright (C) Chemistry Dept., Moscow State University, 2002
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