Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis; Journal of Physics: Conference Series; Vol. 1439 : Modern Problems of Physics and Technology

Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis; Journal of Physics: Conference Series; Vol. 1439 : Modern Problems of Physics and Technology

Bibliographische Detailangaben
Parent link:Journal of Physics: Conference Series
Vol. 1439 : Modern Problems of Physics and Technology.— 2020.— [012040, 6 p.]
Weitere Verfasser: Balachkov M. M. Maxim Mikhailovich, Dolmatov O. Yu. Oleg Yurevich, Kuznetsov M. S. Mikhail Sergeyevich, Kostyuchenko K. S. Kristina Sergeevna, Pimenov N. O. Nikita Olegovich, Permikin A. A. Anton Andreevich
Zusammenfassung:Title screen
The paper describes a technique for obtaining intermetallic matrix materials based on Zr-Al and Ni-Al systems for dispersive nuclear fuel. This type of fuel is planned to be used in existing and future high-temperature nuclear reactors. Physical and mathematical modelling of the process of activation of matrices by neutron radiation showed that upon reaching the value of thermal neutron fluence of the order of 2.76·1021 n·cm-2 , the activity of Zr-Al and Ni-Al matrices was 1.3·1010 and 0.2·1010 Bq/g, respectively. The analysis showed that in terms of exposure of irradiated fuel it is preferable to use a matrix based on the zirconium-aluminium system.
Sprache:Englisch
Veröffentlicht: 2020
Schlagworte:
электронный ресурс
труды учёных ТПУ
нейтронная активация
дисперсионное топливо
ядерное топливо
матричные материалы
ядерные реакторы
физико-математическое моделирование
активация
матрицы
облученное топливо
Online-Zugang:http://earchive.tpu.ru/handle/11683/64884
http://dx.doi.org/10.1088/1742-6596/1347/1/012040
Format: Elektronisch Buchkapitel
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=663824

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