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RBEC-M Lead-Bismuth Cooled Fast Reactor: Optimization of Conceptual Decisions

[+] Author Affiliations
K. Mikityuk, A. Vasiliev, P. Fomichenko, T. Schepetina, S. Subbotin, P. Alekseev

RRC Kurchatov Institute, Moscow, Russia

Paper No. ICONE10-22329, pp. 701-709; 9 pages
  • 10th International Conference on Nuclear Engineering
  • 10th International Conference on Nuclear Engineering, Volume 2
  • Arlington, Virginia, USA, April 14–18, 2002
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-3596-0 | eISBN: 0-7918-3589-8
  • Copyright © 2002 by ASME


A concept of the RBEC lead-bismuth fast reactor is a synthesis, on one hand, experience in development and operation of fast sodium power reactors and reactors with Pb-Bi coolant, and, on the other hand, of large R&D activities on development of the core concept for modified fast sodium reactor. The paper presents improved project RBEC-M, characterized by a number of innovative decisions, which allow to improve safety and cost parameters compared to the basic RBEC project. These innovative decisions include application of nitride fuel based on 15 N, two-circuit scheme without main reactor pumps, gas lift system in the primary circuit, passive reactor auxiliary cooling system, etc.

Copyright © 2002 by ASME



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