Fast Reactor Operating on Uranium–Plutonium Oxide Fuel in a Self-Regulatable Regime |
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Authors: | V. Ya. Gol'din G. A. Pestryakova Yu. V. Troshchiev E. N. Aristova |
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Affiliation: | (1) Russian Academy of Sciences, Institute of Mathematical Simulation, Russia |
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Abstract: | Mathematical simulation is used to show that it is possible to develop a fast reactor operating on uranium–plutonium oxide fuel (UO2)1–x (PuO2)x, the same for all fuel elements in the core, and with uranium carbide in breeding elements with heavy coolant (PbBi eutectic). A self-regulatable regime is obtained in the reactor. This enhances safety while minimizing control. Tailings uranium with 0.1% 235U and a mixture of plutonium isotopes, which is obtained from spent fuel, making it possible to conduct operation in an actinide-closed fuel cycle, is used in the fuel and uranium carbide. 238U is actually consumed in the reactor, but most fission products are produced from 239Pu. |
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