Publication:
Thermogravimetric study of mixed uranium-plutonium fuel for prospective generation IV reactors

Дата
2022
Авторы
Kireev, G. A.
Davydov, A. V.
Skupov, M. V.
Solomatin, I. D.
Krivov, M. P.
Tenishev, A. V.
Journal Title
Journal ISSN
Volume Title
Издатель
Научные группы
Организационные подразделения
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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
© 2022The analysis of the accidental regime of the MNIT fuel reactor facility has indicated a possible scenario of decomposition of the fuel composition with the release of metallic plutonium, which is unacceptable during operation of a nuclear reactor. The present paper studies the behaviour of mixed uranium-plutonium nitride nuclear fuel (MNIT fuel) at high temperatures (up to 2400 K) in a helium flow by thermogravimetry using an STA 449 F1 thermal analyser. The nitride fuel is shown to sublimate at a temperature of about 2000 K. X-ray microanalysis of the samples prior to and after high-temperature testing has established that mass loss in the mixed nitride is primarily due to plutonium evaporation.
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Цитирование
Thermogravimetric study of mixed uranium-plutonium fuel for prospective generation IV reactors / Kireev, G.A. [et al.] // Journal of Nuclear Materials. - 2022. - 567. - 10.1016/j.jnucmat.2022.153798
URI
https://www.doi.org/10.1016/j.jnucmat.2022.153798
 https://www.scopus.com/record/display.uri?eid=2-s2.0-85130612045&origin=resultslist
 http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=Alerting&SrcApp=Alerting&DestApp=WOS_CPL&DestLinkType=FullRecord&UT=WOS:000808362000009
 https://openrepository.mephi.ru/handle/123456789/27936
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