nucВестник НЯЦ РКNNC RK Bulletin1729-75161729-7885Национальный ядерный центр Республики Казахстан10.52676/1729-7885-2020-1-104-111nuc-227Research ArticleСтатьиЭКСПЕРИМЕНТАЛЬНАЯ БАЗА РЕАКТОРА ВВР-К ДЛЯ ИССЛЕДОВАНИЯ ВЫХОДА ТРИТИЯ ИЗ МАТЕРИАЛОВ ПРИ ИХ ОБЛУЧЕНИИEXPERIMENTAL BASE OF THE WWR-K REACTOR FOR IN-SITU INVESTIGATION OF TRITIUM RELEASE FROM MATERIALSШаймерденовА. А.ShaimerdenovA. A.

Алматы

Almaty

ГизатулинШ. Х.GizatulinSh. H.

Алматы

Almaty

НакиповД. А.NakipovD. A.

Алматы

Almaty

КенжинЕ. А.KenzhinYe. A.

Алматы

Almaty

ЧихрайЕ. В.ChikhrayYe. V.

Алматы

Almaty

ЗаурбековаЖ. А.ZaurbekovaZh. A.

Алматы

Almaty

ТоленоваА. У.TolenovaA. U.

Алматы

Almaty

НестеровЕ. А.NesterovE. A.

Томск

Tomsk

КизанэГ.KizaneG.

Рига

Riga

РГП «Институт ядерной физики»КазахстанRSE “Institute of Nuclear Physics”KazakhstanКазНУ им. Аль-ФарабиКазахстанAl-Farabi Kazakh National UniversityKazakhstanКазНУ им. Аль-Фараби; КазНИТУ им. К. И. СатпаеваКазахстанAl-Farabi Kazakh National University; Satbayev UniversityKazakhstanТомский Политехнический УниверситетРоссияTomsk Polytechnic UniversityRussian FederationЛатвийский УниверситетЛатвияUniversity of LatviaLatvia20203003202001104111Copyright © Шаймерденов А.А., Гизатулин Ш.Х., Накипов Д.А., Кенжин Е.А., Чихрай Е.В., Заурбекова Ж.А., Толенова А.У., Нестеров Е.А., Кизанэ Г., 20202020Шаймерденов А.А., Гизатулин Ш.Х., Накипов Д.А., Кенжин Е.А., Чихрай Е.В., Заурбекова Ж.А., Толенова А.У., Нестеров Е.А., Кизанэ Г.Shaimerdenov A.A., Gizatulin S.H., Nakipov D.A., Kenzhin Y.A., Chikhray Y.V., Zaurbekova Z.A., Tolenova A.U., Nesterov E.A., Kizane G.Данная работа распространяется под лицензией Creative Commons Attribution 4.0.This work is licensed under a Creative Commons Attribution 4.0 License.https://journals.nnc.kz/jour/article/view/227

Реактор ВВР-К – это уникальный многоцелевой легководный исследовательский реактор мощностью 6 МВт. Теплоносителем и замедлителем в активной зоне является обессоленная вода, отражатель – бериллий. После завершения процесса перевода реактора на низкообогащенное топливо в реакторе используется диоксид урана, обогащенный до 19,7% по изотопу уран-235. С момента запуска реактора ВВР-К на нем проводятся исследования изменения физико-механических свойств различных материалов. Начиная с 2000 года, на реакторе ВВР-К проводились работы по исследованию материалов термоядерного реактора, а именно эксперименты по исследованию высвобождения трития из литиевой керамики. Была разработана установка для внутриреакторных исследований высвобождения трития из различных материалов-кандидатов бридерного бланкета термоядерного реактора в среде инертного газа. Также была разработана методика оценки времени удержания трития в облучаемых материалах. В 2018 году на реакторе ВВР-К была создана новая установка для исследования материалов термоядерных реакторов, на которой стало возможно проводить эксперименты по облучению образцов в условиях вакуума. В данной работе представлено описание экспериментальных установок и их общие технические возможности применительно к ожидаемым исследованиям выхода трития из литийсодержащих материалов термоядерного реактора на реакторе ВВР-К.

The WWR-K reactor is a unique 6 MW multi-purpose light-water research reactor. Desalinated water is the coolant and moderator, and beryllium is the reflector. Uranium dioxide enriched up to 19.7% on the uranium-235 isotope serves as fuel. Since the launch of the WWR-K reactor, studies of various materials of research reactors have been carried out on it. Beginning in 2000, work was carried out at the WWR-K reactor to study the materials of fusion reactor, namely, experiments to study the release of tritium from lithium ceramics. A facility was developed for in-pile reactor studies of tritium release from various candidate materials for a breeder blanket of a fusion reactor in an inert gas environment. A methodology was also developed for estimating the retention time of tritium in irradiated materials. In 2018, an installation for studying the materials of fusion reactors was created at the WWR-K reactor, at which it became possible to conduct experiments on irradiating samples in a vacuum. In this work, a description of the WWR-K reactor, experimental facilities, and their general technical capabilities as applied to the expected studies of tritium yield from the fusion reactor materials at the WWR-K reactor is presented.

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The authors declare that there are no conflicts of interest present.