Publication:
Optimization of the cold moderator for the new pulsed reactor NEPTUN

Дата
2023
Авторы
Hassan, A. A.
Bulavin, M. V.
Afanasyev, V. V.
Journal Title
Journal ISSN
Volume Title
Издатель
Научные группы
Организационные подразделения
OrgUnit Logo
Организационная единица
Институт ядерной физики и технологий
Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.
Выпуск журнала
Аннотация
The Frank Laboratory of Neutron Physics (FLNP) at the Joint Institute for Nuclear Research (JINR) has begun designing a new research reactor, NEPTUN, to replace the IBR-2M (pulsed fast reactor - the name in russian) reactor, which is expected to be out of service between 2032 and 2036. The IBR-2 reactor is a third-generation neutron source that started working in 1982 at Dubna, Russian Federation. The IBR-2M reactor was successfully modernized in 2012. The NEPTUN reactor is a fourth-generation neutron source that will use Np-237 as a nuclear fuel for the first time. It was studied if mesitylene (1,3,5-trimethylbenzene), which is now being utilized effectively in the reactor IBR-2M, might be used as a cold moderator in the new research reactor NEPTUN with an average thermal power of 15 MWt. A study of five materials used as a cold neutron moderator at various temperatures was also conducted. Longer working times for cold moderator material were another goal of optimization. According to the findings, mesitylene at a temperature of 20 K should be used as a cold moderator to get the greatest neutron flux at a wavelength of 3 ≤ λ ≤ 10 Å. Additionally, ortho hydrogen at 20 K could increases the cold neutron flux with wavelengths, λ ˃ 10 Å.
Описание
Ключевые слова
Mesitylene , Neutron moderator , Neutron Transport , Neutron Detection , Neutron poison , Neutron Activation Analysis
Цитирование
Hassan, A. A. Optimization of the cold moderator for the new pulsed reactor NEPTUN / Hassan, A. A., Bulavin, M. V., Afanasyev, V. V. // Nuclear Engineering and Design. - 2023. - 404. - 10.1016/j.nucengdes.2023.112192
URI
https://www.doi.org/10.1016/j.nucengdes.2023.112192
 https://www.scopus.com/record/display.uri?eid=2-s2.0-85146842109&origin=resultslist
 http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000926654000001
 https://openrepository.mephi.ru/handle/123456789/29916
Коллекции
Публикации