Assessment of the possibility for large-scale 238Pu production in a VVER-1000 power reactor

A. Shmelev, N. Geraskin, V. Apse, G. G. Kulikov, E. G. Kulikov, Vasily B. Glebov
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Abstract

The paper presents the estimates for the possibility for large-scale production of 238Pu in the core of a VVER-1000 power reactor. The Np-fraction of minor actinides extracted from transuranic radioactive waste is proposed to be used as the starting material. The irradiation device with NpO2 fuel elements is installed at the reactor core center. The NpO2 fuel lattice pitch is varied and the irradiation device is surrounded by a heavy moderator layer to create the best possible spectral conditions for large-scale production (~ 3 kg/year) of conditioned plutonium with the required isotopic composition (not less than 85% of 238Pu and not more than 2 ppm of 236Pu). Plutonium with such isotopic composition can be used as the thermal source in thermoelectric radioisotope generators and in cardiac pacemakers. It has been demonstrated that the estimated scale of the 238Pu production in a VVER-type power reactor exceeds considerably the existing scale of its production in research reactors.
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评估在 VVER-1000 型动力反应堆中大规模生产 238Pu 的可能性
本文对在 VVER-1000 型动力反应堆堆芯中大规模生产 238Pu 的可能性进行了估算。建议使用从超铀放射性废物中提取的小锕系元素的镎馏分作为起始材料。带有二氧化铌燃料元件的辐照装置安装在反应堆堆芯中心。二氧化铌燃料的晶格间距是变化的,辐照装置周围有重载慢化剂层,以便为大规模生产(约 3 千克/年)具有所需同位素组成(238Pu 不低于 85%,236Pu 不超过 2 ppm)的有条件钚创造最佳光谱条件。具有这种同位素组成的钚可用作热电放射性同位素发生器和心脏起搏器的热源。事实证明,在 VVER 型动力反应堆中生产 238Pu 的估计规模大大超过了在研究反应堆中生产 238Pu 的现有规模。
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