A. V. Kaplienko, V. V. Lemekhov, Yu. S. Cherepnin, A. V. Moiseyev, A. P. Zhirnov, A. N. Ivanyuta, I. M. Rozhdestvenskiy, D. Yu. Loginov, Ye. R. Mezhina, A. L. Izhutov, Ye. A. Zvir, G. V. Shevlyakov, I. N. Volkova, Ye. G. Batyrbekov, V. V. Baklanov, A. G. Korovikov, A. N. Kotlyar, A. A. Miller, R. A. Irkimbekov, A. D. Vurim
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引用次数: 0
Abstract
Fuel elements with mixed uranium-plutonium nitride fuel were tested in an IGR reactor to justify their application in a BREST-OD-300 reactor. The mid-radial enthalpy limit for the fresh mixed nitride fuel as experimentally determined during IGR launching with fast reactivity input amounted to 167 cal/g. The maximum temperature of 1000 °C and its maintenance for 100 s, comprising one of the design limits for the fuel cladding temperature, was experimentally confirmed. The main results of the performed experiments and post-irradiation studies are analyzed.
期刊介绍：
Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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