Americium Transmutation in the SVBR-100 Reactor  

作　　者：A. V. Gulevich V. A. Eliseev O. G. Komlev I. V. Tormyshev G. I. Toshinsky A. V. Gulevich;V. A. Eliseev;O. G. Komlev;I. V. Tormyshev;G. I. Toshinsky(JSC “SSC RF-IPPE”, Obninsk, Russia;JSC “AKME-Engineering”, Moscow, Russia)

机构地区：[1]JSC “SSC RF-IPPE”, Obninsk, Russia [2]JSC “AKME-Engineering”, Moscow, Russia

出　　处：《World Journal of Nuclear Science and Technology》2020年第3期116-128,共13页核科学与技术国际期刊（英文）

摘　　要：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.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.

关 键 词：SVBR-100 Fast Reactor Nuclear Power Lead-Bismuth Eutectic Minor Actinides AMERICIUM Nuclear Fuel Cycle Neutron Spectrum CORE 

分 类 号：TL9[核科学技术]