Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel; Applied Radiation and Isotopes; Vol. 181

Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel

מידע ביבליוגרפי
Parent link:Applied Radiation and Isotopes
Vol. 181.— 2022.— [110094, 9 p.]
מחבר תאגידי: Национальный исследовательский Томский политехнический университет Инженерная школа ядерных технологий Отделение ядерно-топливного цикла
מחברים אחרים: Irkimbekov R. A. Ruslan Aleksandrovich, Vurim A. D. Aleksandr Davidovich, Bedenko S. V. Sergey Vladimirovich, Vlaskin G. N. Gennadiy Nikolaevich, Suraev A. S. Artur Sergeevich, Vityuk G. A. Galina Anatoljevna, Vega-Carrillo H. R. Hector Rene
סיכום:Title screen
Safe irradiated nuclear fuel (INF) storage of research reactors is ensured by solving issues of protection against ?-irradiation while the neutron component is usually without consideration due to significantly lower intensity. Regarding the low-enriched composite uranium fuel of the IVG.1M reactor that is characterized by a set of elements with low and mean atomic weight where reaction is possible (a, n), evaluation of the neutron component is an indispensable procedure for ensuring radiation safety INF storage. This research suggests a method for neutron component calculation of radiation properties of fresh and irradiated fuel of the IVG.1M reactor, the a-n-component was evaluated. The research results will be useful when choosing a technology for INF storage and for analysis of feasibility to use neutron irradiation with a purpose to control fuel burnout.
Режим доступа: по договору с организацией-держателем ресурса
שפה:אנגלית
יצא לאור: 2022
נושאים:
электронный ресурс
труды учёных ТПУ
the IVG.1M research reactor
low-enriched uranium nuclear fuel
dosimetry(a, n)-reaction
ядерное топливо
реакторы
גישה מקוונת:https://doi.org/10.1016/j.apradiso.2021.110094
פורמט: אלקטרוני Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=666860
תיאור
סיכום:Title screen
Safe irradiated nuclear fuel (INF) storage of research reactors is ensured by solving issues of protection against ?-irradiation while the neutron component is usually without consideration due to significantly lower intensity. Regarding the low-enriched composite uranium fuel of the IVG.1M reactor that is characterized by a set of elements with low and mean atomic weight where reaction is possible (a, n), evaluation of the neutron component is an indispensable procedure for ensuring radiation safety INF storage. This research suggests a method for neutron component calculation of radiation properties of fresh and irradiated fuel of the IVG.1M reactor, the a-n-component was evaluated. The research results will be useful when choosing a technology for INF storage and for analysis of feasibility to use neutron irradiation with a purpose to control fuel burnout.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.1016/j.apradiso.2021.110094

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