Advanced reactor vessel steels for reactors with supercritical coolant parameters

• Published in: Russian metallurgy Metally 2016-09, Vol.2016 (9), p.803-811
• Main Authors: Markov, S. I., Dub, V. S., Lebedev, A. G., Kuleshova, E. A., Balikoev, A. G., Makarycheva, E. V., Tolstykh, D. S., Frolov, A. S., Krikun, E. V.
• Format: Article
• Language: English
• Subjects: Brittleness; Carbon; Chemistry and Materials Science; Composition; Computer simulation; Coolants; Design; Ductile-brittle transition; Heat resistant steels; Iron and steel making; Materials Science; Metallic Materials; Metallurgy; Nickel; Nickel steels; Nonmetallic inclusions; Nuclear reactors; Parameters; Radiation; Reactors; Steel; Strength; Structural steels; Temperature; Transition temperature; Trends
• ISSN: 0036-0295; 1555-6255; 1531-8648
• DOI: 10.1134/S003602951609010X

A set of studies, tests, and technological works is performed to design promising high-strength vessel steels for reactors with supercritical coolant parameters. Compositions and technological parameters are proposed for the production of reference steel (within the limits of the grade composition of 15Kh2NMFA-A steel) and high-nickel steel. These steels are characterized by high properties, including metallurgical quality and service and technological parameters. Steel of the reference composition has high (higher by 15%) strength properties, improved viscoplastic properties, and ductile–brittle transition temperature t c of at most–125°C. The strength properties of the high-nickel steel are higher than those of the existing steels by 40–50% and higher than those of advanced foreign steels by 15–20% at ductile–brittle transition temperature t c of at most–165°C. Moreover, the designed steels are characterized by a low content of harmful impurity elements and nonmetallic inclusions, a fine-grained structure, and a low susceptibility to thermal embrittlement.