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Use of nuclear-inert fuel matrices in fuel element designs
https://doi.org/10.15518/isjaee.2023.04.113-119
Abstract
The paper presents an analysis of the the radiotoxicity of the fission products of the cores of thermal (VVER, RBMK) and fast (FN) neutron reactors, a model of fuel elements with an inert matrix. It is shown that the exclusion of 238U from the fuel composition makes it possible to reduce the radioactivity of the fuel composition for thermal neutron reactors by three orders of magnitude; for fast neutron reactors by 1-2 orders of magnitude compared to traditional fuel compositions containing 238U.
Allows you to reduce the long-term radioactivity created by actinides by more than 2 orders of magnitude.
Russia's experience in the use of highly enriched fuel in research reactors (for example, IVV-2), Topaz nuclear power plant (90% 235U) confirms the results of the analysis to reduce the radioactivity of core and spent nuclear fuel.
About the Authors
G. I. Skvortsov
Ural Federal University named after the First President of Russia B. N. Yeltsin
Russian Federation
Russian Federation
Gleb I. Skvortsov - 6th year student of the Department of Nuclear Power Plants and Renewable Energy Sources
Yekaterinburg
S. E. Shcheklein
Ural Federal University named after the First President of Russia B. N. Yeltsin
Russian Federation
Russian Federation
Sergey E. Shcheklein - Doctor of technical science, professor, head of Atomic Stations and Renewable Energy Sources Department
Yekaterinburg
References
1. Meteorology and atomic energy//US atomic energy commission. Washington, 1955.
2. Nuclear Engineering International: News, 15.1.2020.
3. Methodology for identifying and assessing the radiation situation of a beyond design basis accident of a nuclear power reactor at a nuclear power plant, State standart R, 22.X.XX-2016, (project), Moscow, 2016.
Review
For citations:
Skvortsov G.I., Shcheklein S.E. Use of nuclear-inert fuel matrices in fuel element designs. Alternative Energy and Ecology (ISJAEE). 2023;(4):113-119. (In Russ.) https://doi.org/10.15518/isjaee.2023.04.113-119
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