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Komlev, O.G., Novikova, N.N., Trevgoda, M.M. and Filimonov, Ye.V. (2007) Status and Problems of Computation and Methodological Substantiation of Designing Works on Reactor Facilities with Lead-Bismuth Coolant. Izvestia Vuzov. Yadernaya Energetika, No. 1, 79-91. (In Russian)

has been cited by the following article:

• TITLE: Americium Transmutation in the SVBR-100 Reactor

  AUTHORS: A. V. Gulevich, V. A. Eliseev, O. G. Komlev, I. V. Tormyshev, G. I. Toshinsky

  KEYWORDS: SVBR-100, Fast Reactor, Nuclear Power, Lead-Bismuth Eutectic, Minor Actinides, Americium, Nuclear Fuel Cycle, Neutron Spectrum, Core

  JOURNAL NAME: World Journal of Nuclear Science and Technology, Vol.10 No.3, July 13, 2020

  ABSTRACT: One of the postponed problems of nuclear power (NP) is the problem of the management of long-lived radioactive waste (RAW), and, first of all, with minor actinides (MA), of which americium-241 is the most difficult. The aim of this work is to study the efficiency of americium transmutation in a fast reactor with a heavy liquid metal coolant lead-bismuth eutectic alloy. The article presents the results of calculations of the transmutation of americium in the SVBR-100 reactor using standard uranium oxide fuel with the addition of americium-241. The obtained values of the rate of transmutation of americium are compared with similar values for the SVBR-100 reactors on MOX-fuel and in the BN-800 reactor.