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

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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.

Original languageEnglish
Article number012010
JournalJournal of Physics: Conference Series
Issue number1
Publication statusPublished - 17 Jan 2020
Event8th International Youth Scientific School-Conference on Modern Problems of Physics and Technology, MPPT 2019 - Moscow, Russian Federation
Duration: 15 Apr 201920 Apr 2019


ASJC Scopus subject areas

  • Physics and Astronomy(all)

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