CESIUM SEPARATION FROM SPENT FUEL AND MOLYBDENUM TRIOXIDE JOINT HIGH TEMPERATURE TREATMENT PRODUCT PROCESS MODIFICATION
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.
Authors
- V. N. Momotov (ORCID: https://orcid.org/0000-0002-9514-0692)
- N. O. Pozigun
- V. A. Boldakov
- Anastasia A. Telnova
- Poglyad Sergey S.
- Kornilov Alexander S.
- О С Дмитриева
Institutions
- State Scientific Center - Research Institute of Atomic Reactors (RU)
- National Research Nuclear University MEPhI (RU)
Publication Details
- Journal
- Lomonosov chemistry journal
- Published
- 2024-09-16
- DOI
- https://doi.org/10.55959/msu0579-9384-2-2024-65-5-413-423
- Primary Topic
- Chemical Synthesis and Characterization
- Type
- article
- Field-Weighted Citation Impact
- 0.00