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Title | Simulation of point defects formation in the fuel element of a nuclear power plant’s wave reactor |
Authors |
Opyatyuk, V.V.
Kozlov, I.L. Karchev, K.D. Vistiak, S.V. Kozlov, O.I. Turmanidze, R. |
ORCID | |
Keywords |
process visualization defects spatial distribution fuel rod damage mechanism process innovation |
Type | Article |
Date of Issue | 2023 |
URI | https://essuir.sumdu.edu.ua/handle/123456789/91619 |
Publisher | Sumy State University |
License | Creative Commons Attribution 4.0 International License |
Citation | Opyatyuk V. V., Kozlov I. L., Karchev K. D., Vistiak S. V., Kozlov O. I., Turmanidze R. (2023). Simulation of point defects formation in the fuel element of a nuclear power plant’s wave reactor. Journal of Engineering Sciences, Vol. 10(1), pp. F7-F10, doi: 10.21272/jes.2023.10(1).f2 |
Abstract |
This paper considers the point defects that influence the operation of a wav nuclear power reactor with a
uranium fuel medium. The formed individual point defects or such defect groups can produce a perturbing effect on
the stability of the nuclear reactor operating mode and involve its transition to an unstable state. Studies have been
carried out on the effect on the characteristics of the nuclear burnup wave in a medium with neutron multiplication for
2D geometry. For the calculation, the uranium-thorium fissile medium has been considered. The parametric
calculations were carried out with 235 U different enrichment percents and different values of neutron activation energy.
At that, it was assumed that the wave (flow) reactor stable operation region is located in the range of activation energies
from 10–3
eV to 1 eV or in the region from 2 MeV to 8 MeV. When calculating the neutron flux intensity in a wave
reactor, the influence of point defects and their aggregates on the decelerating elastically scattered neutrons’ flux density
and the flux density of decelerating non-elastically scattered neutrons was considered. The dependences of the point
defects formation rate on the medium fissile temperature for several compositions of the uranium-thorium medium are
obtained. As visually identified, the graphic materials obtained during the calculations are similar to the photos of fuel
rods after the energy campaign. |
Appears in Collections: |
Journal of Engineering Sciences / Журнал інженерних наук |
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Opyatyuk_jes_1_2023.pdf | 467,24 kB | Adobe PDF | 6017 |
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