Abstract

The concept of a fast neutron reactor with a sodium coolant with metallic U–Pu fuel in the core and metallic uranium and thorium in the blankets is considered. The achievement of the required system characteristics for the initial loading and surplus fuel breeding is demonstrated. Several scenarios of the development of a two-component nuclear power system in Russia based on the VVER-type thermal reactors and fast reactors with metallic fuel involving the thorium resources are considered.

中文翻译：

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ium在具有热中子反应堆和快速中子反应堆的核动力系统中的使用

摘要

考虑了一种具有钠冷却剂的快速中子反应堆的概念，该冷却剂的核心为金属U-Pu燃料，毯层为金属铀和th。演示了实现初始装载和多余燃料育种所需的系统特性的过程。考虑了在俄罗斯开发基于VVER型热反应堆和含metallic资源的金属燃料快堆的两组分核电系统的几种方案。