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Information × Registration Number 0214U001382, 0112U007272 , R & D reports Title Influence of KOH and LiOH on kinetic parameters of zirconium alloys oxidation at enhanced burnup/extended fuel cycle popup.stage_title Head Zuyok Valeriy, Registration Date 07-02-2014 Organization "Nuclear Fuel Cycle "Science and Technology Establishment National Science Center "Kharkov Institute of Physics and Technology" popup.description2 Analysis of the scientific and technical information on the influence of alkaline elements, potassium and lithium, on the corrosion resistance and other properties of PWR and WWER fuel cladding during the transition to high burnup and extended fuel cycle is given in the report. The results of the autoclave tests in primary WWER water with different concentrations of alkaline additives and experimental studies of the influence of different concentrations of alkalines KOH and LiOH in the primary WWER coolant during power operation on the corrosion resistance of zirconium alloy E110 are presented. Radiological situation and environmental standards, which are constantly being tightened, leading to the question about the demand to replace corrective additive KOH on LiOH enriched in Li-7. On the other hand, taking into account the global tendencies to improve the safety and reliability of nuclear reactor operation that are dependent on the reliability of the fuel performance, replacement of KOH on LiOH will lead to increased corrosion of the fuel cladding and thus to the decreased reliability of main barrier underway towards radioactive fuel fission products expansion. Product Description popup.authors Грицина В.М. Зуйок В.А. Красноруцький В.С. Петельгузов І. А. Рудь Р.О. Слабоспицька О.О. Трет'яков М.В. popup.nrat_date 2020-04-02 Close