在快中子铀-钍燃料反应堆模型中微量锕系元素嬗变效率Comparison

V. Korobeinikov, V. Kolesov, A. Mikhalev
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引用次数: 1

摘要

就核原料而言,将钍纳入燃料循环的问题几乎无关紧要。然而,考虑到核电的大规模发展,钍的使用似乎是相当自然和合理的。在快中子反应堆中,用传统的铀-钚燃料代替铀-钍燃料将大大减少少量锕系元素的产生,这对已经积累和仍在积累的镅、curium和镎的长寿命放射性同位素的嬗变具有吸引力。由于自然界中不存在铀-233,在核电工业中使用钍需要一个封闭的燃料循环。在开发铀-钍循环的初期,建议用铀-235代替铀-233作为核燃料。研究了在快中子反应堆中进行铀钍循环的微量锕系元素嬗变。已经考虑了这种反应堆堆芯结构的几种方案。已经证明,不均匀放置的镅比均匀放置的嬗变率更高。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparison of the minor actinide transmutation efficiency in models of a fast neutron uranium-thorium fueled reactor
In terms of nuclear raw materials, the issue of involving thorium in the fuel cycle is hardly very relevant. However, in view of the large-scale nuclear power development, the use of thorium seems to be quite natural and reasonable. The substitution of traditional uranium-plutonium fuel for uranium-thorium fuel in fast neutron reactors will significantly reduce the production of minor actinides, which will make it attractive for the transmutation of long-lived radioactive isotopes of americium, curium and neptunium that have already been and are still being accumulated. Due to the absence of uranium-233 in nature, the use of thorium in the nuclear power industry requires a closed fuel cycle. At the initial stage of developing the uranium-thorium cycle, it is proposed to use uranium-235 instead of uranium-233 as nuclear fuel. Studies have been carried out on the transmutation of minor actinides in a fast neutron reactor in which the uranium-thorium cycle is implemented. Several options for the structure of the core of such a reactor have been considered. It has been shown that heterogeneous placement of americium leads to higher rates of its transmutation than homogeneous placement does.
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