Abstract
Two variants of the arrangement of a fast reactor cooled by a eutectic alloy of lead and bismuth are studied. The first one is obtained by solving the problem of minimizing the void coefficient with drying of the central zone of the reactor. The second one is obtained by increasing the power by a factor of 1.5. Both problems contain a constraint for the reliability functionals, characterizing the nominal operating regime of the reactor, and the safety functionals, characterizing the intrinsic self-shielding from ATWS-type accidents.
A fast reactor cooled with the eutectic alloy Pb–Bi possesses a high potential from the standpoint of increasing the power of the power-generating unit while maintaining safety at an acceptable level. 1 figure, 2 tables, 3 references.
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REFERENCES
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V. V. Khromov, A. M. Kuz'min, and V. V. Orlov, Method of Successive Linearization in the Problems of Optimization of Reactors Based on Fast Neutrons [in Russian], Atomizdat, Moscow (1978).
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Okunev, V.S. Power Maximization of a Lead-Bismuth Cooled Fast Reactor. Atomic Energy 90, 247–253 (2001). https://doi.org/10.1023/A:1011332630029
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DOI: https://doi.org/10.1023/A:1011332630029