The Use of Thorium in a Nuclear Power System with Thermal and Fast Neutron Reactors

Bobrov E. A.; Andrianova E. A.; Blandinskiy V. Yu.; Teplov P. S.; Gurin A. V.

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The Use of Thorium in a Nuclear Power System with Thermal and Fast Neutron Reactors

机译：用热速和快中子反应器在核电系统中使用钍

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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.

机译：考虑了快中子反应堆的概念，其中钠冷却剂的堆芯中含有金属铀钚燃料，覆盖层中含有金属铀和钍。演示了初始装载和剩余燃料繁殖所需系统特性的实现。考虑了俄罗斯基于VVER型热核反应堆和使用含钍资源的金属燃料的快堆开发双组分核动力系统的几种情况。

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来源
《Physics of atomic nuclei》 |2020年第8期|共8页
作者
Bobrov E. A.; Andrianova E. A.; Blandinskiy V. Yu.; Teplov P. S.; Gurin A. V.;
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作者单位

Natl Res Ctr Kurchatov Inst Moscow 123182 Russia;

Natl Res Ctr Kurchatov Inst Moscow 123182 Russia;

Natl Res Ctr Kurchatov Inst Moscow 123182 Russia;

Natl Res Ctr Kurchatov Inst Moscow 123182 Russia;

Natl Res Ctr Kurchatov Inst Moscow 123182 Russia;

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原文格式 PDF
正文语种 eng
中图分类原子物理学;原子核物理学、高能物理学;
关键词
thorium; fast neutron reactor; two-component nuclear power system; uraniumamp; 8211; plutonium metallic fuel; Super-BR;

机译：钍;快上的中子反应器;双组分核电力系统;铀＆amp;8211;钚金属燃料;超级布鲁;

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The Use of Thorium in a Nuclear Power System with Thermal and Fast Neutron Reactors

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