Estimating the neutron component of radiation properties of the IVG.1M research reactor irradiated low-enriched fuel / R. A. Irkimbekov, A. D. Vurim, S. V. Bedenko [et al.]

Уровень набора: Applied Radiation and IsotopesАльтернативный автор-лицо: Irkimbekov, R. A., Ruslan Aleksandrovich;Vurim, A. D., Aleksandr Davidovich;Bedenko, S. V., physicist, Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences, 1980-, Sergey Vladimirovich;Vlaskin, G. N., Gennadiy Nikolaevich;Suraev, A. S., Artur Sergeevich;Vityuk, G. A., Galina Anatoljevna;Vega-Carrillo, H. R., Hector ReneКоллективный автор (вторичный): Национальный исследовательский Томский политехнический университет, Инженерная школа ядерных технологий, Отделение ядерно-топливного циклаЯзык: английский.Страна: .Резюме или реферат: 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..Примечания о наличии в документе библиографии/указателя: [References: 45 tit.].Аудитория: .Тематика: электронный ресурс | труды учёных ТПУ | the IVG.1M research reactor | low-enriched uranium nuclear fuel | dosimetry(a, n)-reaction | ядерное топливо | реакторы Ресурсы он-лайн:Щелкните здесь для доступа в онлайн
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[References: 45 tit.]

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.

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