Исследование состояния металла внутрикорпусных устройств реактора ВВЭР после эксплуатации в течение 45 лет. Часть 3. Микроструктура и фазовый состав

Методами просвечивающей электронной микроскопии, растровой электронной микроскопии, а также методом атомно-зондовой томографии проведены исследования радиационно-индуцированных составляющих структуры металла (сталь марки 08Х18Н10Т) фрагментов выгородки реактора энергоблока № 3 НВОАЭС после эксплуатации в течение 45 лет. Фрагменты отличались повреждающей дозой (от 14 до 43 сна) и температурой облучения (от 285 до 315°С). Определены плотность и размеры карбидов и карбонитридов титана, дислокационных петель, пор, радиационно-индуцированных сегрегаций и наноразмерных преципитатов. Оценен вклад структурных составляющих в радиационное упрочнение металла.

внутрикорпусные устройства реактора, нейтронное облучение, нержавеющая сталь, радиационно-индуцированное изменение структуры

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