Open AccessEvaluation of neutron activation of intermetallic matrices for dispersive nuclear fuel obtained by SH-synthesis
Author(s) -
M. M. Balachov,
O. Yu. Dolmatov,
М. С. Кузнецов,
K. S. Kostyuchenko,
Nikita O. Pimenov,
А. А. Пермикин
Publication year - 2020
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1439/1/012010
Subject(s) - intermetallic , nuclear fuel , materials science , aluminium , neutron , spent nuclear fuel , matrix (chemical analysis) , zirconium , neutron activation , irradiation , neutron temperature , neutron activation analysis , fluence , radiochemistry , nuclear chemistry , nuclear engineering , chemistry , metallurgy , nuclear physics , composite material , physics , alloy , engineering
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⋅10 21 n⋅cm −2 , the activity of Zr-Al and Ni-Al matrices was 1.3 ⋅ 10 10 and 0.2⋅10 10 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.