Research of the state of internal surfaces of a supercritical water loop after a session of irradiation

• Дата: 2020
• Автори: Azarov, A.I., Bakai, A.S., Boriskin, V.N., Bocharov, V.A., Gorenko, Yu.V., Dolzhek, M.A., Zaitsev, E.I., Momot, V.A., Solodovnikov, V.I., Tytov, V.Yu., Shelepko, S.V.
• Формат: Стаття
• Мова: English
• Опубліковано: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2020
• Назва видання: Вопросы атомной науки и техники
• Теми: Application of accelerators in radiation technologies
• Онлайн доступ: http://dspace.nbuv.gov.ua/handle/123456789/194555
• Назва журналу: Digital Library of Periodicals of National Academy of Sciences of Ukraine
• Цитувати: Research of the state of internal surfaces of a supercritical water loop after a session of irradiation / A.I. Azarov, A.S. Bakai, V.N. Boriskin, V.A. Bocharov, Yu.V. Gorenko, M.A. Dolzhek, E.I. Zaitsev, V.A. Momot, V.I. Solodovnikov, V.Yu. Tytov, S.V. Shelepko // Problems of Atomic Science and Technology. — 2020. — № 3. — С. 180-182. — Бібліогр.: 5 назв. — англ.

Made of austenitic steel at the NSC KIPT, the supercritical water convection loop Loop-1a was running for more than 500 hours in the first experimental session (in 2011). The materials tested in the loop were placed into a stream of water (more than 50 g/s) at a temperature of 350…400°C, a pressure of 23… 25 MPa, and were irradiated by an electron beam with an energy of 10 MeV. Sediments that emerged on the inner surface of the loop were examined. The sediment mainly consisted of compounds of calcium and iron mixed with other elements. There is a possibility to increase corrosion induced by radiation due to dislocation damage, hydrogenation of metal and under the impact of active oxygen.