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Information × Registration Number 0219U004191, 0116U006656 , R & D reports Title " Development high-entropy alloys and creation on their basis of a new class of oxide dispersion strengthened materials with high radiation resistance and improved physical and mechanical properties" popup.stage_title Head Tikhonovsky Mikhail Andreyevich, Кандидат фізико-математичних наук Registration Date 10-04-2019 Organization National Science Center "Kharkiv Institute of Physics & Technology" popup.description2 The ingots of cobalt-free high-entropy alloys of three compositions (in at.%) are proposed and manufactured by the arc melting method: E 30-2 (18Cr-40Fe-28Mn-14Ni), E 31-2 (18Cr-28Fe-27Mn-28Ni) and E 32- 2 (20Cr-40Fe-20Mn-20Ni) and its microstructural characteristics were investigated. Experimental technology of mechanical doping of high-entropy alloys by nanooxides of the 80X2O3-20ZrO2 system and methods of compaction of the obtained powders have been developed. Oxide precipitates for all alloys were characterized by the presence of both small particles about 10 nm in size and large ones (up to 150 nm). The density of oxide precipitates is ~1014 cm-3. The composition of the oxides includes not only Y and Zr, but also matrix elements of the alloys. The main mechanism of corrosion damage in liquid lead at a temperature of 480° C is intergranular corrosion, and at a temperature of 580° C is added also diffusion of oxygen from the melt to the matrix, which causes internal oxidation of chromium and manganese. The use of high-entropy alloys in contact with melt lead should be recommended up to a temperature of 500° C with fine grains. Moreover, the alloy E 32-2 has the advantage both in the initial state and dispersed strengthened by oxides. The yield strength of ODS HEAs increased by 2 times compared with the initial state, the tensile strength remained almost unchanged, and the ductility was about 20% at a temperature of 20° C. High-entropy alloys are much less susceptible to radiation hardening and loss of ductility compared to traditional materials of nuclear energy - austenitic steels Х18Н10Т and SS316 - for which the hardening almost doubles after the same irradiation. This indicates the promise of using high-entropy alloys as materials for new-generation nuclear reactors. Product Description popup.authors Андрієвська Н. Василенко Р. Великодний О. Воєводін В. Кісляк І. Кальченко О. Кравчишин Т. Кухар І. Літовченко С. Лук'яненко О. Мельник Х. Назаренко Є. О. Єфімов Онищенко Л. Пилипенко М. Стоєв П. Сторожилов Г. Тихоновський М. Федірко В. Чишкала В. popup.nrat_date 2020-04-02 Close