Study of the possibility of using thorium in fast power reactors

Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology Pub Date : 1966-09-01 DOI:10.1016/0368-3230(66)90161-3

A.I. Leipunskii, O.D. Kazachkovskii, S.B. Shikhov, V.M. Murogov

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Abstract

The results of studying the possibilities of using ²³³U and thorium in a reactor system with breeding are described. It is shown that the most promising from the point of view of fuel doubling time is the combined use of ²³³U-Th and ²³⁹Pu-²³⁸U in a mixed fast-reactor fuel cycle on condition that the thorium is placed in the shields and ²³³U, ²³⁹Pu and ²³⁸U in the cores.

The burning and regeneration of ²³⁸U and ²³⁹Pu in a mixed fuel cycle is effected in such a way that the ratio of the quantity of each remains constant. The doubling time of a system of fast reactors operating on a mixed fuel cycle mode is substantially less than the doubling time of reactors using only ²³⁸U and thorium. The main raw material in the mixed fuel cycle is thorium.

A method of obtaining isotopically pure ²³⁸U with a 231U content ∼ 10⁻⁴ per cent is given.

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在快堆中使用钍的可能性研究

介绍了在有增殖的反应堆系统中使用233U和钍的可能性的研究结果。结果表明，从燃料倍增时间的角度来看，在混合快堆燃料循环中，在将钍放置在屏蔽层中，将233U、239Pu和238U放置在堆芯的条件下，233U- th和239Pu-238U联合使用是最有希望的。在混合燃料循环中，238U和239Pu的燃烧和再生是在两者数量的比例保持不变的情况下实现的。在混合燃料循环模式下运行的快堆系统的倍增时间大大少于仅使用238U和钍的反应堆的倍增时间。混合燃料循环的主要原料是钍。给出了一种获得231U含量为~ 10−4%的同位素纯238U的方法。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Journal of Nuclear Energy. Parts A/B. Reactor Science and Technology

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