WAYS TO IMPROVE THE COEFFICIENT REPRODUCTION OF QUICK REACTORS WITH OXIDE FUEL AND SODIUM COOLANT
https://doi.org/10.26583/GNS-2019-03-10
EDN: CKKJPF
Abstract
This article presents the results of a numerical study of ways to increase the reproduction rate of fast reactors with oxide fuel and sodium coolant. The purpose of this work is to study and detect fuel or fuel combination with the best technical and economic indicators for the BN-800 reactor facility which will increase not only economic indicators but also the efficiency of the entire pre-reactor cycle. Since over time the problems associated with a decrease in the amount of U235 which leads to an increase in its price and an increase in the amount of accumulated Pu which in the initial time is obtained in the framework of the military industry, worsen throughout the world. But today there is a need to look for ways to compensate for these phenomena with the priority of reliable and safe operation of a nuclear installation from the reprocessing of spent nuclear fuel (spent nuclear fuel) from WWER and RBMK. The paper examines the effects of several important factors on the performance of the reactor and on economic performance. These factors are the use of different fuels and fuel combinations, the geometrical dimensions of the reactor, the distribution of enriched fuel in the core, as well as the change in the specific volume of fuel within the permitted limits.
About the Authors
A. K. Harutyunyan
National Research Nuclear University Moscow Engineering Physics Institute (NRNU MEPhI)
Russian Federation
Russian Federation
S. B. Vygovskiy
National Research Nuclear University Moscow Engineering Physics Institute (NRNU MEPhI)
Russian Federation
Russian Federation
A. G. Khachatryan
National Research Nuclear University Moscow Engineering Physics Institute (NRNU MEPhI)
Russian Federation
Russian Federation
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Review
For citations:
Harutyunyan A.K., Vygovskiy S.B., Khachatryan A.G. WAYS TO IMPROVE THE COEFFICIENT REPRODUCTION OF QUICK REACTORS WITH OXIDE FUEL AND SODIUM COOLANT. Global Nuclear Safety. 2019;(3):89-100. (In Russ.) https://doi.org/10.26583/GNS-2019-03-10. EDN: CKKJPF
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