Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis

M. M. Balachov, O. Yu Dolmatov, M. S. Kuznetsov, K. S. Kostyuchenko, N. O. Pimenov, A. A. Permikin

Отделение ядерно-топливного цикла

Результат исследования: Материалы для журнала

Аннотация

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.

Язык оригинала	Английский
Артикульный номер	012010
Журнал	Journal of Physics: Conference Series
Том	1439
Номер выпуска	1
DOI	https://doi.org/10.1088/1742-6596/1439/1/012010
Статус публикации	Опубликовано - 17 янв 2020
Событие	8th International Youth Scientific School-Conference on Modern Problems of Physics and Technology, MPPT 2019 - Moscow, Российская Федерация Длительность: 15 апр 2019 → 20 апр 2019

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ASJC Scopus subject areas

Physics and Astronomy(all)

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Balachov, M. M., Dolmatov, O. Y., Kuznetsov, M. S., Kostyuchenko, K. S., Pimenov, N. O., & Permikin, A. A. (2020). Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis. Journal of Physics: Conference Series, 1439(1), [012010]. https://doi.org/10.1088/1742-6596/1439/1/012010

Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis. / Balachov, M. M.; Dolmatov, O. Yu ; Kuznetsov, M. S.; Kostyuchenko, K. S.; Pimenov, N. O.; Permikin, A. A.

В: Journal of Physics: Conference Series, Том 1439, № 1, 012010, 17.01.2020.

Результат исследования: Материалы для журнала

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abstract = "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.",

author = "Balachov, {M. M.} and Dolmatov, {O. Yu} and Kuznetsov, {M. S.} and Kostyuchenko, {K. S.} and Pimenov, {N. O.} and Permikin, {A. A.}",

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T1 - Evaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis

AU - Balachov, M. M.

AU - Dolmatov, O. Yu

AU - Kuznetsov, M. S.

AU - Kostyuchenko, K. S.

AU - Pimenov, N. O.

AU - Permikin, A. A.

PY - 2020/1/17

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N2 - 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.

AB - 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.

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Доступ к документу

10.1088/1742-6596/1439/1/012010