DOI: 10.55176/2414-1038-2021-2-82-104
Авторы
Курина И.С., Фролова М.Ю., Чесноков Е.А.
Организация
АО «Государственный научный центр Российской Федерации – Физико-энергетический институт имени А.И. Лейпунского», Обнинск, Россия
Курина И.С. – ведущий научный сотрудник, кандидат технических наук, доцент. Контакты: 249033, Калужская обл., Обнинск, пл. Бондаренко, 1. Тел.: +7 (484) 399-86-32; e-mail: Адрес электронной почты защищен от спам-ботов. Для просмотра адреса в браузере должен быть включен Javascript..
Фролова М.Ю. – инженер 1 категории.
Чесноков Е.А. – руководитель группы.
Аннотация
В статье приводится обзор известных зарубежных научных публикаций, посвящённых исследованию свойств металлического ядерного топлива на основе U-Zr, по составу близкого к U-10 мас. % Zr, широко используемого в реакторах.
Рассмотрены отличия микроструктуры топлива, изготовленного разными способами: экструзией и литьём. Показано влияние термического отжига на изменение микроструктуры сплава. Представлены фотографии, полученные с помощью оптического и электронного микроскопов, а также кристаллографические данные для двух фаз: α-U и δ-UZr2.
Известные литературные данные свидетельствуют, что плотность богатых ураном U-Zr сплавов соответствует правилу смесей. В качестве теоретической плотности сплава U-10 мас. % Zr (U-22,5 ат. % Zr) следует принять значение 16,2 г/см3.
Приведены результаты термофизических исследований топлива U-10 мас. % Zr с применением метода дифференциальной сканирующей калориметрии (ДСК). Представлены данные по измерениям термического расширения U-Zr сплавов, а также теплопроводности. Большинство данных по теплопроводности либо рассчитаны на основе измеренных плотности, удельной теплоёмкости и температуропроводности, либо получены моделированием.
Ключевые слова
металлическое топливо, сплав U-10 мас. % Zr, экструзия, литьё, микроструктура, отжиг, плотность, фазовый состав, термическое расширение, теплопроводность
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