Open AccessRESEARCH OF THE STATE OF INTERNAL SURFACES OF A SUPERCRITICAL WATER LOOP AFTER A SESSION OF IRRADIATION
Author(s) -
А. И. Азаров,
A. S. Bakaı̆,
В.Н. Борискин,
Vladimir N. Bocharov,
Yu.V. Gorenko,
M.A. Dolzhek,
E.I. Zaitsev,
V.A. Momot,
V.I. Solodovnikov,
V.Yu. Tytov,
S.V. Shelepko
Publication year - 2020
Publication title -
problems of atomic science and technology
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.216
H-Index - 17
eISSN - 1562-6016
pISSN - 1682-9344
DOI - 10.46813/2020-127-180
Subject(s) - supercritical fluid , irradiation , materials science , loop (graph theory) , oxygen , metal , austenite , corrosion , composite material , metallurgy , chemistry , thermodynamics , nuclear physics , physics , mathematics , microstructure , organic chemistry , combinatorics
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.