SVBR-100反应堆中的镅嬗变

A. Gulevich, V. Eliseev, O. Komlev, I. Tormyshev, G. Toshinsky
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引用次数: 1

摘要

核能(NP)的一个延迟问题是长寿命放射性废物(RAW)的管理问题,首先是微量锕系元素(MA)的管理,其中镅-241是最困难的。本工作的目的是研究在快堆中用重金属冷却剂铅-铋共晶合金进行镅嬗变的效率。本文介绍了在SVBR-100反应堆中使用标准氧化铀燃料并添加镅-241的情况下,对镅嬗变的计算结果。将所获得的镅嬗变速率值与使用MOX燃料的SVBR-100反应堆和BN-800反应堆中的类似值进行比较。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Americium Transmutation in the SVBR-100 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.
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